Page 1 of 103

Method to Assess Internal Dose Using 

Gross Alpha, Beta, and Gamma

Bioassay and Air Sampling at the

Lawrence Berkeley National Laboratory

White Paper

Rev. 00

National Institute for Occupational Safety and Health 

September 18, 2017

Stephen Spanos 

Oak Ridge Associated Universities Team

Reviewed by Lara Hughes

Division of Compensation Analysis and Support 

This is a working document prepared by NIOSH’s Division of Compensation Analysis and Support (DCAS) or its contractor for use in discussions 

with the ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or 

ABRWH (or their technical support and review contractors) positions unless specifically marked as such. This document represents preliminary 

positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any 

information that is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

September 18, 2017

Page 2 of 103

This is a working document prepared by NIOSH’s Division of Compensation Analysis and Support (DCAS) or its contractor for use in discussions 

with the ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or 

ABRWH (or their technical support and review contractors) positions unless specifically marked as such. This document represents preliminary 

positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any 

information that is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.

TABLE OF CONTENTS

EXECUTIVE SUMMARY ............................................................................................................ 6

INTRODUCTION .......................................................................................................................... 6

AIR SAMPLING ............................................................................................................................ 7

METHOD FOR ASSESSING INTERNAL DOSE ...................................................................... 11

Gross Alpha Bioassay Results .................................................................................................. 12

Gross Beta Bioassay Results ..................................................................................................... 15

Gross Gamma Bioassay Results ............................................................................................... 17

Internal Dose from Short-Lived (T1/2 <100 Days) Radionuclides (Including Unmonitored 

Long-Lived Radionuclides Not Detected by Gross Bioassay Methods) .................................. 19

Guidance for Assessing Internal Dose Using Gross Alpha, Gross Beta, and Gross Gamma 

Bioassay Results Below the Minimum Detectable Activity ..................................................... 23

Alpha Radionuclides ............................................................................................................. 23

Beta Radionuclides ............................................................................................................... 24

Gamma Radionuclides .......................................................................................................... 25

EXAMPLE: MISSED DOSE RECONSTRUCTION OF LONG- AND SHORT-LIVED 

ALPHA, BETA, AND GAMMA RADIONUCLIDES ................................................................ 27

Long-Lived (T1/2 >100 days) Internal Dose, January 1, 1969, Through December 31, 1971 27

Short-Lived (T1/2 <100 days) Internal Dose, January 1, 1969, Through December 31, 1971 29

Final Internal Dose, January 1, 1969, Through December 31, 1971 ........................................ 30

Unmonitored Worker Internal Dose, January 1, 1967, Through December 31, 1968 .............. 30

Guidance for Assessing Internal Dose Using Positive Bioassay Results Where the 

Radionuclide is Not Identified .................................................................................................. 32

Alpha Radionuclides ............................................................................................................. 32

Beta Radionuclides ............................................................................................................... 33

Gamma Radionuclides .......................................................................................................... 33

Guidance for Assessing Internal Dose Using Positive Bioassay Results Where the 

Radionuclide is Identified ......................................................................................................... 34

Alpha Radionuclides ............................................................................................................. 34

Beta Radionuclides ............................................................................................................... 34

Gamma Radionuclides .......................................................................................................... 34

Assessing Internal Dose to an Unmonitored Worker ............................................................... 35

Alpha Radionuclides ............................................................................................................. 35
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

September 18, 2017

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with the ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or 

ABRWH (or their technical support and review contractors) positions unless specifically marked as such. This document represents preliminary 

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information that is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.

Beta Radionuclides ............................................................................................................... 35

Gamma Radionuclides .......................................................................................................... 36

REFERENCES ............................................................................................................................. 55

ATTACHMENT A ....................................................................................................................... 60

Overview ................................................................................................................................... 60

Radionuclides with Half-Lives Less than 100 Days ............................................................. 61

Radionuclides with Half-Lives Greater than 100 Days ........................................................ 61

Input Sources ............................................................................................................................ 62

Worksheet Descriptions ............................................................................................................ 63

Breathing Zone Data ............................................................................................................. 63

Doses Based on Bioassay...................................................................................................... 63

ICRP 68 DCFs ...................................................................................................................... 63

Alpha Breathing Zone Int Rates ........................................................................................... 63

Unmonitored Alpha Organ Doses ......................................................................................... 64

Gross Alpha Bio Organ Doses .............................................................................................. 65

Unmonitored Worker 67-68 Alpha Doses ............................................................................ 67

BG Breathing Zone Intake Rates .......................................................................................... 68

Unmonitored BG Organ Doses ............................................................................................. 69

Gross Beta Bio Organ Doses ................................................................................................ 70

Gross Gamma Bio Organ Doses ........................................................................................... 72

Unmonitored Worker BG Doses 67-68 ................................................................................ 73

Example Calculations ............................................................................................................... 74

Alpha Breathing Zone Int Rates ........................................................................................... 74

Unmonitored Alpha Organ Doses ......................................................................................... 75

Gross Alpha Bio Organ Doses .............................................................................................. 76

BG Breathing Zone Intake Rates .......................................................................................... 79

Unmonitored BG Organ Doses ............................................................................................. 80

Gross Beta Bioassay Organ Doses ........................................................................................ 82

Gross Gamma Bio Organ Doses ........................................................................................... 84

ATTACHMENT B ....................................................................................................................... 88

LBNL Air Concentration Data Exposure Model Description .................................................. 88

1962....................................................................................................................................... 89
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

September 18, 2017

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with the ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or 

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information that is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.

January 1963 Through August 1963 ..................................................................................... 91

September 1963 Through 1987 ............................................................................................. 92

December 1984 ..................................................................................................................... 95

January 1993 Through June 1993 ......................................................................................... 95

ATTACHMENT C ..................................................................................................................... 101

Short-Lived Radionuclide Exclusions .................................................................................... 101

Tables

Table 1. 95th-Percentile Alpha and Beta/Gamma Annual Air Concentrations. .......................... 10

Table 2. Radionuclides with T1/2 Less than 20 Hours. ............................................................... 11

Table 3. Long-Lived (T1/2 >100 days) Alpha Radionuclide Branching Fractions. .................... 12

Table 4. Long-Lived (T1/2 >100 days) Alpha Radionuclide Intake Rates Based on Air 

Concentration Data. ...................................................................................................................... 14

Table 5. Long-Lived (T1/2 >100 days) Beta Radionuclide Branching Fractions. ...................... 15

Table 6. Long-Lived (T1/2 >100 days) Beta Radionuclide Intake Rates Based on Air 

Concentration Data. ...................................................................................................................... 16

Table 7. Long-Lived (T1/2 >100 days) Gamma Radionuclide Photon Yields. ........................... 17

Table 8. Long-Lived (T1/2 >100 days) Gamma Radionuclide Intake Rates Based on Air 

Concentration Data. ...................................................................................................................... 19

Table 9. Short-Lived (T1/2 <100 days) Radionuclide Intake Rates Based on Air Concentration 

Data. .............................................................................................................................................. 20

Table 10. Example Calculation Employment Information. ......................................................... 27

Table 11. Example Calculation Cancer Information. .................................................................. 27

Table 12. Example Calculation Bioassay Information. ............................................................... 27

Table 13. Example Calculation Air Concentration Information. ................................................. 27

Table 14. Alpha Internal Dose Summary (rem), 1969 to 1971. .................................................. 28

Table 15. Beta Internal Dose Summary (rem), 1969 to 1971. ..................................................... 28

Table 16. Gamma Internal Dose Summary (rem), 1969 to 1971................................................. 28

Table 17a. Short-Lived Internal Committed Dose Summary for Radionuclide Selection (rem), 

1969 to 1971. ................................................................................................................................ 29

Table 17b. Short-Lived Internal Dose Summary (rem), 1969 to 1971. ....................................... 29

Table 18. Internal Dose Summary (rem), 1969 to 1971. ............................................................. 30

Table 19. Additional Alpha Emitters for Unmonitored Workers, 1967 to 1968. ........................ 31
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

September 18, 2017

Page 5 of 103

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with the ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or 

ABRWH (or their technical support and review contractors) positions unless specifically marked as such. This document represents preliminary 

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information that is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.

Table 20a. Unmonitored Worker Internal Committed Dose Summary (rem), 1967 to 1968. ..... 31

Table 20b. Unmonitored Worker Internal Dose Summary (rem), 1967 to 1968. ........................ 32

Table 21a. Gross Alpha Method. ................................................................................................. 37

Table 21b. Gross Alpha Method (Continued). ............................................................................. 38

Table 22a. Gross Alpha Method. ................................................................................................. 39

Table 22b. Summary of Table 22a. .............................................................................................. 39

Table 23a. Gross Beta Method..................................................................................................... 40

Table 23b. Gross Beta Method (Continued). ............................................................................... 41

Table 24a. Gross Gamma Method. .............................................................................................. 42

Table 24b. Gross Gamma Method (Continued). .......................................................................... 44

Table 25a. Gross Beta and Gross Gamma Methods. ................................................................... 46

Table 25b. Summary of Table 25a. .............................................................................................. 48

Table 26a. Unmonitored Worker Alpha Method. ........................................................................ 49

Table 26b. Summary of Table 26a. .............................................................................................. 50

Table 27a. Unmonitored Worker Beta and Gamma Methods. .................................................... 51

Table 27b. Summary of Table 27a. .............................................................................................. 54

Table A-1. Example Calculation Employment Information. ....................................................... 60

Table A-2. Example Calculation Cancer Information. ................................................................ 60

Table A-3. Example Calculation Bioassay Information. ............................................................. 60

Table A-4. Example Calculation Air Concentration Information. .............................................. 60

Table B-1. Uncensored Alpha Months, Total Months, and Number of Air Sampling 

Locations. ...................................................................................................................................... 89

Table B-2. Uncensored Beta/Gamma Months, Total Months, and Number of Air Sampling 

Locations. ...................................................................................................................................... 91

Table B-3. Filter Queen BZ Locations Referenced to a Radionuclide-Specific Percent MPC. .. 92

Table B-4. Filter Queen BZ Locations Sampled. ........................................................................ 94

Table B-5. Alpha BZ Data Details. .............................................................................................. 97

Table B-6. Beta/Gamma BZ Data Details. .................................................................................. 99

Table C-1. Radionuclides with Half-Lives Less than 20 Hours. ............................................... 101

Table C-2. External Doses Based on Air Submersion. .............................................................. 102
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

September 18, 2017

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with the ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or 

ABRWH (or their technical support and review contractors) positions unless specifically marked as such. This document represents preliminary 

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information that is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.

EXECUTIVE SUMMARY

This white paper provides methods for assessing internal dose using gross alpha, gross beta, and 

gross gamma bioassay results and air sampling data at Lawrence Berkeley National Laboratory 

(LBNL). Methods are provided for assessing gross alpha, gross beta, and gross gamma results 

bioassay results that are below and above the minimum detectable activity. Air sampling data is 

used to assign internal dose from shorter-lived radionuclides that may not be detected by 

bioassay. In addition, a method is provided for assigning internal dose to an unmonitored worker 

using air sampling data. Example calculations are provided validating the proof of concept. 

This method would apply for 1962 and later. The methods described in this white paper will 

need to be implemented in an internal dose tool. 

INTRODUCTION

The Lawrence Berkeley National Laboratory monitored workers using gross alpha, beta, and 

gamma bioassay analyses from the start of its bioassay program in 1962 at least into the mid1990s. The gross alpha and beta analyses were used primarily for screening purposes. The gross 

beta procedure was done after gamma-counting the gamma emitters. This would not have 

identified the specific radionuclides, so positive gross alpha and beta results typically were 

followed by specific procedures to identify the particular radionuclides. Gamma emitters were 

analyzed via gamma spectroscopy (Low-Beer 1964; Buckley 1969; LBNL 1985a, 1985b; LBL 

1989). LBNL did not typically identify the radionuclides for results that were less than the 

minimum detection limit for these bioassay methods.

Bioassay requests were generally made either once or twice per year for each employee in the 

bioassay program. Workers who worked with or in areas that contained unsealed radioactive 

materials typically received bioassays (Soule 1962; Schmidt et al. 1973). Therefore, based on 

the typical LBNL bioassay monitoring frequencies, a single bioassay result indicates that the 

worker had, at most, one year of internal exposure potential before the date of the bioassay. For 

example, a single bioassay on December 31, 1967, implies, at most, an intake potential from 

January 1, 1967, through December 31, 1967. Non-routine bioassays were made in cases where 

other evidence (survey results, air samples, wound from contaminated object) indicated a 

potential significant exposure (Howe 1961). All other employment periods with no bioassay 

indicate a potential exposure to environmental levels only. 

When non-detectable gross alpha, beta, and gamma bioassay results are indicated in a worker’s 

records, there typically is no information as to the specific radionuclides to which they might 

have been exposed. Bioassay lists might provide this information (LBL 1979, 1981a; LBNL 

1985a). In cases where no specific radionuclide information is available, a method for assessing 

missed dose from gross alpha, beta, and gamma bioassay results is necessary. A list of potential 

alpha, beta, and gamma emitters was compiled based on Table 2-1 of the Site Profile for the 

Lawrence Berkeley National Laboratory (ORAUT 2010), bioassay lists (LBL 1979, 1981a; 

LBNL 1985a), and the Pit Room inventory list from 1952 to 1981 (LBNL 1952). In compiling 

these lists, there were radionuclides with half-lives less than 100 days, which this document 
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

September 18, 2017

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with the ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or 

ABRWH (or their technical support and review contractors) positions unless specifically marked as such. This document represents preliminary 

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refers to as “short-lived.” These short-lived radionuclides are typically not expected to be 

detected with bioassay sampling frequencies of one year or six months, and can usually be 

considered unmonitored radionuclides. In addition, there are some “long-lived” radionuclides 

whose half-lives were greater than 100 days that were not detected by the gross bioassay 

methods. These were included in the short-lived radionuclides assessed by air concentration 

data, as discussed below. This document refers to radionuclides with half-lives greater than or 

equal to 100 days as “long-lived.” 

AIR SAMPLING

LBNL performed air sampling in locations where accidental releases of airborne radioactivity 

were likely (UCRL 1964; LBL 1981b). LBNL also maintained permanently installed air 

samplers that operated continuously in various locations. The air samples were changed weekly 

in locations of moderate experimental activity and daily in locations of intense experimental 

activity. These air samples were also called breathing-zone (BZ) air samples, but were actually 

work area air samples.

The limitations of work area air sampling were recognized in the early days at LBNL. Air 

samplers did not normally reflect general room area atmosphere, but only a closely 

circumscribed volume near the sampling head (Thaxter 1955). Lawrence Berkeley National 

Laboratory (LBL 1981b) noted: 

Our air samples are not good representative samples of breathing air. Air currents 

are so unpredictable that air even a few inches away from a person’s nose can be 

quite different from that which he breathes. Air samples give only a rough idea of 

an individual’s exposure, and for that reason, any radioactivity detected should be 

taken seriously, even if only a small fraction of MPC. 

There was general guidance on the placement of air samplers that indicates (LBL 1981b): 

Generally, the sampler should be downwind from the potential source(s) of 

radioactivity, and close to where the people are working. Often this is impossible 

to achieve with a fixed sampler location, but it is good to keep the ideals in mind 

when working out some practical location. In many cases, the best location will be 

at the principal exhaust from the room. In typical labs this will be the hood(s).

Guidance on air sampler placement was provided in the early days at LBNL (LBL 1951): 

Keep the Filter Queen close to the scene of radioactive operations such as gloved 

boxes and hoods. When radioactive operations are moved to another place in the 

room the Filter Queen should be moved accordingly.

In addition (LBL 1981b), 
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

September 18, 2017

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with the ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or 

ABRWH (or their technical support and review contractors) positions unless specifically marked as such. This document represents preliminary 

positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any 

information that is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.

Air samplers serve a dual purpose. Besides supplying a record of “breathing zone” air 

quality, air samplers can also serve as a detector of “spills”. Sometimes a “hot” air 

sample is observed before their direct detection of surface contamination. Also, the 

sensitivity is sufficient to detect small leakages, enabling corrective measures to be taken 

to avoid future larger spills.

A 1953 memorandum, “Sampling Methods and Requirements for Estimating Airborne 

Radioparticulate Hazards” (Thaxter 1953), indicated that because LBNL was a research facility, 

technical contamination was not tolerated as it could invalidate weeks of research. LBNL 

vigorously sought to achieve no airborne contamination. It used high efficiency exhaust air 

cleaning in enclosures. Nuisance contamination levels were lower by several orders of 

magnitude than permissible levels on the health bases. This operational philosophy is reflected 

in the monthly summary air sample reports that listed BZ locations whose monthly average air 

concentrations were greater than or equal to 1% of the maximum permissible concentration 

(MPC) discussed below. A review of this monthly summary air sample data indicated very few 

air sample locations that had monthly average air concentrations greater than or equal to 1% of 

the MPC.

BZ samples were collected for various locations at LBNL. There are monthly summary reports 

that list BZ locations that were greater than or equal to 1% of the MPC for alpha and beta 

emitters. There are also computer printouts of air concentration data for the LBNL BZ air 

sampling locations. These BZ air concentration data were collected as part of the LBNL Dual 

Data Entry Phase I and II BZ data effort. The available computer printouts of air concentration 

data for LBNL from site data capture efforts was not as complete as the monthly summary report 

data that listed BZ locations that were greater than or equal to 1% of the MPC for alpha and beta 

emitters. As a result, the monthly summary report data was used as the primary source for the air 

sampling data. The use of the monthly summary report data also saved considerable time in data 

entry. The computer printout BZ air concentration data was used to fill in missing data from the 

monthly summary reports. The LBNL Dual Data Entry Phase I effort consisted of compiling a 

database of the monthly summary air sample reports that listed BZ locations whose monthly 

average air concentrations were greater than or equal to 1% of the MPC. This data ranged from 

1962 through 1987, and was the majority of the air sample data used. Earlier monthly air sample 

summary reports, from 1962 through mid-1963, did not report monthly average air 

concentrations. There were computer printouts of monthly average air concentrations data for 

1962 and 1963 that were used to determine the annual average air concentrations for these years. 

There were also some missing monthly air sample reports in the mid to late 1980’s. The LBNL 

Dual Data Entry Phase II effort consisted of compiling a database of available monthly air 

sample report data from computer printouts for 1962 through August 1963, December 1984, and 

1993. This data was used to fill in data for unavailable years or months from the LBNL Dual 

Data Entry Phase I effort. Details of the air sample data used in the assessment are provided in 

Attachment B.
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

September 18, 2017

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A statistical reduction of these air sample data determined the 95th-percentile annual average air 

concentration based on the annual average air concentrations of all sample locations (ORAUT 

2017b). It should be noted that LBNL performed continuous 24-hour air sampling, typically on 

a daily or weekly basis. The 95th-percentile annual average air concentrations from the Oak 

Ridge Associated Universities Team (ORAUT 2017b) were multiplied by 4.2 (168/40 hours) to 

adjust for a 40-hour work-week exposure. The factor 4.2 represents the upper bound adjustment 

assuming weekly air sampling. The 95th-percentile annual average air concentrations adjusted 

for continuous 24-hour air sampling are shown in Table 1 below. These BZ data can be used to 

determine the internal dose from unmonitored and missed doses associated with gross alpha, 

beta, and gamma radionuclides for an LBNL worker.

The 95th-percentile annual average air concentrations are considered bounding values. 

Multiplying all 24-hour air samples by 4.2 to adjust for a 40-hour work-week exposure provides 

a positive bias in the 95th-percentile annual average air concentrations. Also, as mentioned 

earlier, is that most of the research at LBNL has been short term, typically on the order of weeks. 

It is unlikely that a worker would have been continuously exposed to these air concentration 

levels of radionuclides in the workplace for an entire year. In addition, the monthly summary 

report data used from 1963 through 1987 only contained air sampling locations that had monthly 

average air concentrations greater than or equal to 1% of the reference MPC. These reported 

results corresponded to, at most, only a few percent of the total number of air samples taken for 

any year. These unreported air sample locations from 1963 through 1987 were filled in with 

censored air concentration values equal to 1% of the reference MPC. These unreported results 

corresponded to, at least, approximately 97% of the total number of air samples taken for any 

year. It should also be noted that LBNL reported monthly average air concentrations in 

computer printouts of air concentration data that were less than 1% of the reference MPC

censoring limit. 

A description of the model used to determine the 95th-percentile annual average air 

concentrations in Table 1 is presented in Attachment B.

The extension of the 1987 air concentration data through 1992 and the 1993 air concentration 

data for later years is a reasonable assumption. Over time, the number of air sampling locations 

decreased at LBNL. Attachment B provides information on the numbers of air samples assumed 

for 1964 through 1987. In addition, a 1994 memorandum indicated that if the risk was low and 

sample results were continually negative, the sampling was to be discontinued. Over the 

previous 12 months, the number of sampled locations decreased for this reason 

(Schoonover 1994). 

Air samples were typically counted 72 hours after removal to allow for decay of the short-lived 

radon and thoron progeny (Peck 1964). There was no decay correction originally applied to 

these air samples. All BZ radionuclide air concentrations used in the dose reconstruction 

methodology were decay-corrected back 72 hours. The list of radionuclides with half-lives less 

than 20 hours, along with their decay-corrected average air concentrations, is shown in Table 2. 
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

September 18, 2017

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with the ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or 

ABRWH (or their technical support and review contractors) positions unless specifically marked as such. This document represents preliminary 

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Table 1. 95th-Percentile Alpha and Beta/Gamma Annual Air Concentrations.

Year

95th-Percentile Alpha Annual 

Air Concentration (pCi/m3)

95th-Percentile Beta/Gamma Annual 

Air Concentration (pCi/m3)

1962 0.0235 17.226

1963 0.0190 20.703

1964 0.0378 4.200

1965 0.0392 4.200

1966 0.0168 4.200

1967 0.0220 4.200

1968 0.0267 4.200

1969 0.0195 4.200

1970 0.0336 4.200

1971 0.0092 4.200

1972 0.0305 4.200

1973 0.0084 4.200

1974 0.0266 4.302

1975 0.0132 4.200

1976 0.0084 4.200

1977 0.0087 5.157

1978 0.0112 4.200

1979 0.0084 4.200

1980 0.0119 4.200

1981 0.0138 4.200

1982 0.0265 4.200

1983 0.0084 4.200

1984 0.0207 6.475

1985 0.0084 4.200

1986 0.0084 4.200

1987 0.0087 4.200a

1993 0.0071b 0.133c

a. 1987 beta/gamma air concentration can be extended through 1992.

b. 1993 alpha air concentration can be extended for 1988 and later years. 

c. 1993 beta/gamma air concentration can be extended for later years. 

Short-lived radionuclide activities that are decay-corrected back 72 hours, such as those in 

Table 2, cannot be produced at levels to maintain the continuous exposures without leaving 

significant field contamination in the work areas. 

Based on the above, short-lived radionuclides with half-lives less than 12.7 hours were excluded 

from the potential unmonitored radionuclides. The excluded short-lived radionuclides were: 

1. Gamma emitters: 

Carbon-11, 60Cu, 63Zn, 104Ag, 224Ac, 99mTc, 127Cs, 62Zn, 175Ta.

2. Beta emitters:

Indium-112, 239U, 49Sc, 68Ga, 18F, 149Nd, 195Ir, 228Ac, 127Te, 212Pb, 42K.
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

September 18, 2017

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Table 2. Radionuclides with T1/2 Less than 20 Hours.

Radionuclide Emitter Half-Life

Beta Branching 

Fraction/Photon 

Yield

Decay-Corrected Annual 

Average Air Concentration 

(pCi/m3)

a

In-112 Beta 14.97 min 0.44 6.79E+87

U-239 Beta 23.45 min 1 1.17E+56

Sc-49 Beta 57.2 min 1 2.26E+23

Ga-68 Beta 67.71 min 1 6.69E+19

F-18 Beta 109.77 min 1 2.94E+12

Nd-149 Beta 1.728 hr 1 1.46E+13

Ir-195 Beta 2.5 hr 1 1.95E+09

Ac-228 Beta 6.16 hr 0.997 1.39E+04

Te-127 Beta 9.35 hr 1 8.73E+02

Pb-212 Beta 10.64 hr 1 4.57E+02

K-42 Beta 12.36 hr 1 2.38E+02

Cu-64 Beta 12.701 hr 0.39 5.47E+02

Nb-90 Beta 14.6 hr 1 1.28E+02

Na-24 Beta 15 hr 1 1.17E+02

Zr-97 Beta 16.9 hr 1 8.04E+01

Pt-197 Beta 18.3 hr 1 6.42E+01

C-11 Gamma 20.39 min 2.43E-06 1.01E+70

Cu-60 Gamma 23.7 min 1.99E+00 1.52E+55

Zn-63 Gamma 38.47 min 1.73E-01 1.52E+35

Ag-104 Gamma 69.2 min 3.06E+00 8.44E+18

Ac-224 Gamma 2.78 hr 6.72E-01 3.90E+08

Tc-99m Gamma 6.015 hr 5.12E-02 3.29E+05

Cs-127 Gamma 6.25 hr 9.17E-01 1.34E+04

Zn-62 Gamma 9.186 hr 8.98E-01 1.07E+03

Ta-175 Gamma 10.5 hr 1.28E+00 3.81E+02

Y-86 Gamma 14.74 hr 3.20E+00 3.88E+01

Br-76 Gamma 16.2 hr 1.73E+00 5.29E+01

Zr-86 Gamma 16.5 hr 1.21E+00 7.17E+01

Co-55 Gamma 17.54 hr 1.31E+00 5.50E+01

a. Air concentrations are also corrected for beta branching fraction of photon yield.

Please refer to Attachment C for more details on the short-lived radionuclide exclusions. 

METHOD FOR ASSESSING INTERNAL DOSE

The method for assessing the internal dose from gross alpha, beta, and gamma bioassay results is 

presented below. This method is a demonstration of the concept. The final method would be 

incorporated into an internal dose reconstruction tool for efficiency purposes. This method 

would apply for 1962 and later.

It should also be noted that the International Commission on Radiological Protection 68 (ICRP 

1995) dose conversion factor (DCF) and half-life data were obtained from Rad Toolbox versions 

2.0 and 3.0. As a result, there might be some differences in radionuclide half-lives in this 
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

September 18, 2017

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document. The current radionuclide data will be incorporated into the dose reconstruction 

implementation tool. 

An example dose reconstruction is provided following this section to demonstrate the concept 

presented in this section for assessing gross alpha, beta, and gamma bioassay results below the 

minimum detectable activity (MDA). Tables 4, 6, 8, and 9 below provide intake rates based on 

the highest 95th-percentile alpha and beta/gamma annual air concentrations for 1967 through 

1971 (i.e., 1970) employment period assumed for the example. Using the highest 95th-percentile 

alpha and beta/gamma annual air concentrations for the 1967 through 1971 example dose 

reconstruction is an overestimating efficiency measure used for demonstration purposes of the 

concept presented below. 

Gross Alpha Bioassay Results 

Table 3 lists alpha-emitting radionuclides at LBNL with half-lives greater than 100 days, along 

with their branching fractions. 

Table 3. Long-Lived (T1/2 >100 days) Alpha

Radionuclide Branching Fractions. 

Radionuclide Alpha Branching Fractions

Am-241 1

Am-243 1

Cf-249 1

Cf-250 0.9992

Cf-252 0.9691

Cm-242 1

Cm-243 0.9971

Cm-244 1

Cm-245 1

Cm-246 0.9997

Cm-248 0.9174

Es-253 1

Es-254 1

Np-237 1

Pa-231 1

Pu-236 1

Pu-238 1

Pu-239 1

Pu-240 1

Pu-242 1

Pu-244 0.9988

Th-228 1

Th-229 1

Th-230 1

Th-232 1

Ac-227 0.0138
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

September 18, 2017

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The bioassay would be assessed for missed dose for each long-lived alpha-emitting radionuclide. 

The alpha branching fraction (Table 3) must be included when determining the sample activity or 

MDA for a given radionuclide when starting with a gross result. The reported urine sample 

value is divided by the branching fraction; the MDA is divided by the branching fraction and a 

factor of 2 for the missed dose adjustment. 

The calculated intake rates from the gross alpha bioassay result are then tabulated for all of the 

radionuclides based on the solubility type that yielded the largest dose. 

Missed dose assumes a constant exposure to a theoretical missed intake that may or may not 

have occurred. By considering all of the available data, bioassay detection limits and workplace 

air sampling data, a more accurate upper bound of the potential non-detected internal exposure 

can be estimated. Therefore, the air sampling data, typically being more sensitive, should be 

used to limit the missed dose associated with a hypothetical intake associated with the detection 

limit. To do this, the calculated missed intake rates associated with the bioassay data, for each 

radionuclide, are compared to the intake rates determined from the BZ air monitoring data (see 

Table 4). The annual alpha intake rates based on BZ data for each of these radionuclides were 

determined by assuming the highest 95th-percentile annual air concentration (i.e., 1970) in Table 

1 for the assumed exposure period of 1967 through 1971 in the example dose reconstruction 

presented below. The more limiting intake rate between the bioassay and BZ data is used to 

calculate the missed dose to the organ of interest. Air sampling data shall not be used to limit 

intakes based on positive bioassay data. The doses from all of the radionuclides are then 

compared to each other, and the radionuclide with the largest dose to the organ of interest is 

assigned.
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

September 18, 2017

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Table 4. Long-Lived (T1/2 >100 days) Alpha Radionuclide

Intake Rates Based on Air Concentration Data.

Radionuclide

Annual Alpha Intake Rate Based on 

BZ Data (dpm/day)

Am-241 0.49

Am-243 0.49

Cf-249 0.49

Cf-250 0.49

Cf-252 0.51

Cm-242 0.50

Cm-243 0.49

Cm-244 0.49

Cm-245 0.49

Cm-246 0.49

Cm-248 0.53

Es-254 0.49

Np-237 0.49

Pa-231 0.49

Pu-236 0.49

Pu-238 0.49

Pu-239 0.49

Pu-240 0.49

Pu-242 0.49

Pu-244 0.49

Th-228 0.49

Th-229 0.49

Th-230 0.49

Th-232 0.49

Ac-227 35.55

NOTE: These intakes rates are based on the 1970 alpha air 

concentration in Table 1. This is the highest alpha air 

concentration for the exposure period of 1967 through 1971 

used in the example dose reconstruction presented below. 
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

September 18, 2017

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ABRWH (or their technical support and review contractors) positions unless specifically marked as such. This document represents preliminary 

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Gross Beta Bioassay Results 

Table 5 lists the long-lived beta-emitting radionuclides used at LBNL with half-lives greater than 

100 days, along with their branching fractions. 

Table 5. Long-Lived (T1/2 >100 days) Beta Radionuclide 

Branching Fractions. 

Radionuclide Beta Branching Fractions

Ta-182 1

Tm-170 0.9987

Ca-45 1

Ag-110m 0.9864

Ce-144 1

Bk-249 1

Ru-106 1

Tm-171 1

Cs-134 0.999997

Pm-147 1

Sb-125 1

Tl-204 0.971

Co-60 1

Ra-228 1

Os-194 1

Eu-154 0.9998

Eu-152 0.279

Pu-241 0.99998

Pb-210 0.9999981

Sr-90 1

Cs-137 1

Ni-63 1

Tb-158 0.166

Ho-166m 1

Nb-94 1

Tc-99 1

Cl-36 0.981

Cd-113 1

The bioassay would be assessed for missed dose for each long-lived beta-emitting radionuclide. 

The beta branching fraction (Table 5) must be included when determining the sample activity or 

MDA for a given radionuclide when starting with a gross result. The reported urine sample 

value is divided by the branching fraction; the MDA is divided by the branching fraction and a 

factor of 2 for the missed dose adjustment. 

The calculated intake rates from the gross beta bioassay result are then tabulated for all of the 

radionuclides based on the solubility type that yielded the largest dose.

Missed dose assumes a constant exposure to a theoretical missed intake that may or may not 

have occurred. By considering all of the available data, bioassay detection limits and workplace 
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

September 18, 2017

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ABRWH (or their technical support and review contractors) positions unless specifically marked as such. This document represents preliminary 

positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any 

information that is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.

air sampling data, a more accurate upper bound of the potential non-detected internal exposure 

can be estimated. Therefore, the air sampling data, typically being more sensitive, should be 

used to limit the missed dose associated with a hypothetical intake associated with the detection 

limit. To do this, the calculated missed intake rates associated with the bioassay data, for each 

radionuclide, are compared to the intake rates determined from the BZ air monitoring data (see 

Table 6). 

Table 6. Long-Lived (T1/2 >100 days) Beta Radionuclide 

Intake Rates Based on Air Concentration Data. 

Radionuclide

Annual Beta Intake Rate Based on 

BZ Data (dpm/day)

a

Ta-182 62.43

Tm-170 62.39

Ca-45 62.10

Ag-110m 62.67

Ce-144 61.76

Bk-249 61.71

Ru-106 61.66

Tm-171 61.49

Cs-134 61.48

Pm-147 61.44

Sb-125 61.43

Tl-204 63.23

Co-60 61.37

Ra-228 61.37

Os-194 61.37

Eu-154 61.36

Eu-152 219.84

Pu-241 61.33

Pb-210 61.32

Sr-90 61.32

Cs-137 61.32

Ni-63 61.31

Tb-158 369.34

Ho-166m 61.31

Nb-94 61.31

Tc-99 61.31

Cl-36 62.50

Cd-113 61.31

a. These intakes rates are based on the 1970 beta/gamma air 

concentration in Table 1. This is the highest beta/gamma 

concentration for the exposure period of 1967 through 1971 used

in the example dose reconstruction presented below. 

The annual beta intake rates based on BZ data for each of these radionuclides were determined 

by assuming the highest 95th-percentile annual air concentration (i.e., 1970) in Table 1 for the 

assumed exposure period of 1967 through 1971 in the example dose reconstruction presented 

below. The more limiting intake rate between the bioassay and BZ data is used to calculate the 
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

September 18, 2017

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missed dose to the organ of interest. Air sampling data shall not be used to limit intakes based 

on positive bioassay data. The doses from all of the radionuclides are then compared to each 

other, and the radionuclide with the largest dose to the organ of interest is assigned. 

Gross Gamma Bioassay Results 

Table 7 lists the long-lived photon-emitting radionuclides used at LBNL with half-lives greater 

than 100 days, along with their photon yield. 

Table 7. Long-Lived (T1/2 >100 days) Gamma Radionuclide 

Photon Yields. 

Radionuclide Photon Yield (Gammas/Disintegration)

Y-88 1.94

Sn-113 0.0185

Te-123m 0.843

Se-75 1.82

W-181 0.0111

Tm-170 0.0326

Re-184m 0.884

Au-195 0.125

Gd-153 0.535

Zn-65 0.508

Ag-110m 3.21

Pm-143 0.385

Co-57 1.06

Mn-54 1.0

Sm-145 0.128

Pm-144 2.44

Cd-109 0.0361

Hf-172 0.502

Cs-134 2.23

Na-22 0.999

Gd-151 0.158

Rh-101 1.42

Co-60 2.0

Eu-154 1.63

Ba-133 1.36

Eu-152 1.58

Pm-145 0.0283

Bi-207 1.8

Ti-44 1.83

Pt-193 0.211

Ag-108m 2.79

Tb-158 1.04

Al-26 1.03

The bioassay would be assessed for missed dose for each long-lived gamma-emitting 

radionuclide. The photon yield (listed in Table 7) must be included when determining the 
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

September 18, 2017

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sample activity or MDA for a given radionuclide when starting with a gross result. The reported 

urine sample value is divided by the photon yield; the MDA is divided by photon yield and a 

factor of 2 for the missed dose adjustment. 

The calculated intake rates from the gross gamma bioassay result are then tabulated for all of the 

radionuclides based on the solubility type that yielded the largest dose. 

Missed dose assumes a constant exposure to a theoretical missed intake that may or may not 

have occurred. By considering all of the available data, bioassay detection limits and workplace 

air sampling data, a more accurate upper bound of the potential non-detected internal exposure 

can be estimated. Therefore, the air sampling data, typically being more sensitive, should be 

used to limit the missed dose associated with a hypothetical intake associated with the detection 

limit. To do this, the calculated intake rates from bioassay data for each radionuclide are 

compared to the intake rates determined from the BZ air monitoring data (see Table 8). The 

annual gamma intake rates based on BZ data for each of these radionuclides were determined by 

assuming the highest 95th-percentile annual air concentration (i.e., 1970) in Table 1 for the 

assumed exposure period of 1967 through 1971 in the example dose reconstruction presented 

below. The more limiting intake rate between the bioassay and BZ data is used to calculate the 

missed dose to the organ of interest. Air sampling data shall not be used to limit intakes based 

on positive bioassay data. The doses from all of the radionuclides are then compared to each 

other, and the radionuclide with the largest dose to the organ of interest is assigned as the final 

dose. 
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

September 18, 2017

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Table 8. Long-Lived (T1/2 >100 days) Gamma Radionuclide

Intake Rates Based on Air Concentration Data.

Radionuclide

Annual Gamma Intake Rate Based 

on BZ Data (dpm/day)a

Y-88 32.31

Sn-113 3,374.38

Te-123m 74.04

Se-75 34.33

W-181 5,603.86

Tm-170 1,911.87

Re-184m 70.24

Au-195 496.47

Gd-153 115.69

Zn-65 121.82

Ag-110m 19.25

Pm-143 160.50

Co-57 58.50

Mn-54 61.73

Sm-145 481.91

Pm-144 25.24

Cd-109 1,705.45

Hf-172 122.53

Cs-134 27.58

Na-22 61.48

Gd-151 388.55

Rh-101 43.13

Co-60 30.70

Eu-154 37.57

Ba-133 45.07

Eu-152 38.94

Pm-145 2,170.14

Bi-207 34.08

Ti-44 33.60

Pt-193 290.59

Ag-108m 21.99

Tb-158 59.01

Al-26 59.81

a. These intakes rates are based on the 1970 beta/gamma air 

concentration in Table 1. This is the highest beta/gamma 

concentration for the exposure period of 1967 through 1971 used in

the example dose reconstruction presented below.

Internal Dose from Short-Lived (T1/2 <100 Days) Radionuclides (Including Unmonitored 

Long-Lived Radionuclides Not Detected by Gross Bioassay Methods) 

Table 9 lists radionuclides with a half-life of less than 100 days except for those radionuclides 

removed earlier due to half-lives shorter than 12.7 hours. These radionuclides, because of their 

short half-lives, generally are not assumed to be detected by the gross alpha, beta, and gamma 

bioassay methods due to the typical internal monitoring frequency of one year. Table 9 also 
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

September 18, 2017

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includes several long-lived radionuclides not detected by the gross alpha or gross gamma 

methods. 

Table 9. Short-Lived (T1/2 <100 days) Radionuclide Intake 

Rates Based on Air Concentration Data.

Radionuclide Emission Type

Intake Rate 

(dpm/day)a

Ac-225 Alpha 0.60

Th-227 Alpha 0.55

Es-253 Alpha 0.54

Sm-146b Alpha 0.49

Gd-148b Alpha 0.49

Po-208b Alpha 0.49

Cu-64 Beta 7,990.72

Nb-90 Beta 1,869.55

Na-24 Beta 1,706.70

Zr-97 Beta 1,174.20

Pt-197 Beta 936.81

Ho-166 Beta 394.54

Os-193 Beta 323.47

Ce-143 Beta 278.08

Br-82 Beta 251.99

Sc-48 Beta 192.04

Sm-153 Beta 178.46

Cd-115 Beta 155.91

Y-90 Beta 133.69

As-71 Beta 132.41

Re-186 Beta 114.93

Np-239 Beta 148.22

Au-198 Beta 132.56

Sb-122 Beta 135.68

Au-199 Beta 118.89

Yb-175 Beta 100.70

Lu-177 Beta 83.58

Tb-161 Beta 82.83

Ag-111 Beta 81.04

P-32 Beta 70.91

Os-191 Beta 70.17

Rb-86 Beta 68.54

Th-234 Beta 66.83

P-33 Beta 66.54

Pa-233 Beta 66.22

Ce-141 Beta 65.36

Nb-95 Beta 65.04

Ru-103 Beta 64.64

Hf-181 Beta 64.39

Fe-59 Beta 64.24
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

September 18, 2017

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Radionuclide Emission Type

Intake Rate 

(dpm/day)a

Hg-203 Beta 64.11

Sr-89 Beta 63.89

Y-91 Beta 63.53

Sb-124 Beta 63.46

Zr-95 Beta 63.33

W-188 Beta 63.17

Tb-160 Beta 63.10

Ir-192 Beta 66.28

W-185 Beta 63.03

Sc-46 Beta 62.85

S-35 Beta 14.95

Y-86 Gamma 566.46

Br-76 Gamma 771.53

Zr-86 Gamma 1,046.74

Co-55 Gamma 803.57

Rh-100 Gamma 290.59

Ni-57 Gamma 215.53

Sb-119 Gamma 1,392.58

Au-194 Gamma 162.18

Am-240 Gamma 162.74

Br-77 Gamma 195.20

Ga-67 Gamma 134.26

Re-186 Gamma 1,012.77

Ba-128 Gamma 762.77

In-111 Gamma 69.27

Tl-201 Gamma 916.05

Pd-100 Gamma 85.13

Mn-52 Gamma 29.64

Ag-106m Gamma 20.89

Cs-131 Gamma 93.02

Ba-131 Gamma 58.17

Rh-99 Gamma 44.92

V-48 Gamma 33.39

Te-121 Gamma 69.44

Sr-82 Gamma 111.92

Cr-51 Gamma 672.29

Yb-169 Gamma 44.93

Ag-105 Gamma 48.71

Be-7 Gamma 616.51

Sr-85 Gamma 64.59

Hf-175 Gamma 67.27

Re-183 Gamma 117.92

Co-58 Gamma 62.76

Co-56 Gamma 25.16

Zr-88 Gamma 62.86

Os-185 Gamma 62.37

Fe-55c Gamma 215.80
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

September 18, 2017

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Radionuclide Emission Type

Intake Rate 

(dpm/day)a

Hg-194c Gamma 248.52

Te-123c Gamma 77.66

a. These intakes rates are based on the 1970 alpha and 

beta/gamma air concentrations in Table 1. These are the 

highest alpha and beta/gamma concentration for the exposure 

period of 1967 through 1971 used in example dose 

reconstruction presented below. 

b. Long-lived radionuclide not detected by gross alpha method 

but picked up by air monitoring.

c. Decay energy likely too low for bioassay but might be counted 

on air sample.

Annual intake rates for each of these radionuclides were determined by assuming the highest 

95th-percentile annual air concentration (i.e., 1970) in Table 1 for the assumed exposure period of 

1967 through 1971 in the example dose reconstruction presented below. These measured air 

concentrations were adjusted as appropriate for the emission rate or gamma yield of the detected 

radiation type. 

These intake rates are then multiplied by ICRP (1995) inhalation DCFs, as shown in the example 

in Tables 24a and 24b, to determine the radionuclide that yields the highest organ committed 

dose for the beta and gamma emitters. This is an efficiency measure that is used to determine the 

radionuclide selection. Because the Interactive RadioEpidemiological Program (IREP) cannot 

accept a 50-year committed dose as input, the intake rate for that particular radionuclide is then 

run using the Integrated Modules for Bioassay Analysis (IMBA) or the Chronic Annual Dose 

Workbook (CAD) to determine the annual equivalent internal doses out to the cancer diagnosis 

date. 

Based on these results:

• The dose reconstructor should assign dose from short-lived (T1/2 <100 days) alpha

radionuclides for each year the worker submitted a bioassay sample and the BZ intake 

rate was not used to assess the dose from the long-lived alpha radionuclide. In the case 

where the BZ data was used to assess the long-lived alpha radionuclide, the dose from the 

short-lived alpha radionuclide that results in the largest dose to the organ of interest 

should be compared to the dose from the long-lived alpha radionuclide. The one that 

results in the largest dose to the organ of interest should be assigned, but not both (in 

order not to double count the activity from the BZ data). 

• The dose reconstructor should assign dose from short-lived (T1/2<100 days) beta 

radionuclides for each year the worker submitted a bioassay sample and the BZ intake 

rate was not used to assess the dose from the long-lived beta radionuclide. In the case 

where the BZ data was used to assess the long-lived beta radionuclide, the dose from the 

short-lived beta radionuclide that results in the largest dose to the organ of interest should 
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

September 18, 2017

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be compared to the dose from the long-lived beta radionuclide. The one that results in 

the largest dose to the organ of interest should be assigned, but not both (in order not to 

double count the activity from the BZ data). 

• The dose reconstructor should assign dose from short-lived (T1/2<100 days) gamma 

radionuclides for each year the worker submitted a bioassay sample and the BZ intake 

rate was not used to assess the dose from the long-lived gamma radionuclide. In the case 

where the BZ data was used to assess the long-lived gamma radionuclide, the dose from 

the short-lived gamma radionuclide that results in the largest dose to the organ of interest 

should be compared to the dose from the long-lived gamma radionuclide. The one that 

results in the largest dose to the organ of interest should be assigned, but not both (in 

order not to double count the activity from the BZ data).

The following summarizes the steps to assess internal dose using gross alpha, gross beta, and 

gross gamma bioassay results below the MDA, and air sampling results at LBNL. Steps for 

assessing positive bioassay results are also provided, following this section.

Guidance for Assessing Internal Dose Using Gross Alpha, Gross Beta, and Gross Gamma 

Bioassay Results Below the Minimum Detectable Activity

Alpha Radionuclides: 

1. Calculate the dose from long-lived alpha radionuclides. 

a. For each radionuclide, calculate the intake rate and missed dose for each 

solubility type based on urinalysis data. 

b. For each radionuclide, select the intake rate/solubility type combination yielding 

the largest internal dose based on urinalysis data. 

c. For each radionuclide, calculate the intake rate based on BZ data.

d. For each radionuclide, select the smaller of the intake rates based on urinalysis 

results (step 1.b) and based on the BZ data (step 1.c). 

e. For each radionuclide, calculate the missed dose based on the results of step 1.d. 

f. Select the radionuclide yielding the largest dose in step 1.e. 

2. Calculate the dose from short-lived alpha radionuclides. 

a. For each radionuclide, determine the annual intake based on BZ data. 

b. For each radionuclide, select the solubility type that yields the largest DCF for the 

organ. 
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

September 18, 2017

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c. For each radionuclide, multiply the annual intake by the DCF selected in step 2.b. 

d. Select the radionuclide yielding the largest committed dose. 

e. Determine the internal dose for the annual intake of the radionuclide yielding the 

largest committed dose using IMBA or CAD. 

3. Dose assignment. 

a. For each year of assumed intake, the urinalysis results yielded the largest dose in 

step 1.f: 

i. Assign the dose from the long-lived alpha emitter selected in step 1.f, and

ii. Assign the dose from the short-lived alpha radionuclide selected in step 

2.e. 

b. For each year of assumed intake, the BZ intake rate yielded the largest dose from 

the long-lived alpha radionuclide (step 1.f): 

i. Compare the dose from the short-lived alpha radionuclide that results in 

the largest dose (from step 2.d) to the dose from the long-lived alpha 

radionuclide (step 1.f). 

ii. From the results of step 3.b.i, assign only the intake that results in the 

largest dose to the organ of interest. 

Beta Radionuclides: 

1. Calculate the dose from long-lived beta radionuclides. 

a. For each radionuclide, calculate the intake rate and missed dose for each 

solubility type based on urinalysis data. 

b. For each radionuclide, select the intake rate/solubility type combination yielding 

the largest internal dose based on urinalysis data. 

c. For each radionuclide, calculate the intake rate based on BZ data.

d. For each radionuclide, select the smaller of the intake rates based on urinalysis 

results (step 1.b) and based on the BZ data (step 1.c).

e. For each radionuclide, calculate the missed dose based on the results of step 1.d. 

f. Select the radionuclide yielding the largest dose in step 1.e. 
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

September 18, 2017

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2. Calculate the dose from short-lived beta radionuclides. 

a. For each radionuclide, determine the annual intake based on BZ data. 

b. For each radionuclide, select the solubility type that yields the largest DCF for the 

organ. 

c. For each radionuclide, multiply the annual intake by the DCF selected in step 2.b. 

d. Select the radionuclide yielding the largest committed dose. 

e. Determine the internal dose for the annual intake of the radionuclide yielding the 

largest committed dose using IMBA or CAD. 

3. Dose assignment. 

a. For each year the urinalysis results yielded the largest dose in step 1.f: 

i. Assign the dose from the long-lived beta emitter selected in step 1.f, and

ii. Assign the dose from the short-lived beta radionuclide selected in step 2.e. 

b. For each year the BZ intake rate yielded the largest dose from the long-lived beta 

radionuclide (step 1.f): 

i. Compare the dose from the short-lived beta radionuclide that results in the 

largest dose (from step 2.d) to the dose from the long-lived beta 

radionuclide (step 1.f). 

ii. From the results of step 3.b.i, assign only the intake that results in the 

largest dose to the organ of interest. 

Gamma Radionuclides: 

1. Calculate the dose from long-lived gamma radionuclides. 

a. For each radionuclide, calculate the intake rate and missed dose for each 

solubility type based on urinalysis data. 

b. For each radionuclide, select the intake rate/solubility type combination yielding 

the largest internal dose based on urinalysis data. 

c. For each radionuclide, calculate the intake rate based on BZ data.
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

September 18, 2017

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d. For each radionuclide, select the smaller of the intake rates based on urinalysis 

results (step 1.b) and based on the BZ data (step 1.c). 

e. For each radionuclide, calculate the missed dose based on the results of step 1.d. 

f. Select the radionuclide yielding the largest dose in step 1.e. 

2. Calculate the dose from short-lived gamma radionuclides. 

a. For each radionuclide, determine the annual intake based on BZ data. 

b. For each radionuclide, select the solubility type that yields the largest DCF for the 

organ. 

c. For each radionuclide, multiply the annual intake by the DCF selected in step 2.b. 

d. Select the radionuclide yielding the largest committed dose. 

e. Determine the internal dose for the annual intake of the radionuclide yielding the 

largest committed dose using IMBA or CAD. 

3. Dose assignment. 

a. For each year the urinalysis results yielded the largest dose in step 1.f: 

i. Assign the dose from the long-lived gamma emitter selected in step 1.f, 

and

ii. Assign the dose from the short-lived gamma radionuclide selected in step 

2.e. 

b. For each year the BZ intake rate yielded the largest dose from the long-lived 

gamma radionuclide (step 1.f): 

i. Compare the dose from the short-lived gamma radionuclide that results in 

the largest dose (from step 2.d) to the dose from the long-lived beta 

radionuclide (step 1.f). 

ii. From the results of step 3.b.i, assign only the intake that results in the 

largest dose to the organ of interest. 
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

September 18, 2017

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EXAMPLE: MISSED DOSE RECONSTRUCTION OF LONG- AND SHORT-LIVED 

ALPHA, BETA, AND GAMMA RADIONUCLIDES

The example presented below is for missed dose for an unknown work location and doses to 

several organs of interest. 

All missed dose calculations based on bioassay are based upon the MDA/2 to calculate the mode 

value in accordance with Section 3.3.1 in ORAUT (2014). 

Table 10. Example Calculation Employment Information.

Employment Period 01/01/1967–12/31/1971

Work Location Unknown

Internal Monitored Period 01/01/1969–12/31/1971

Table 11. Example Calculation Cancer Information.

Cancer Date of Diagnosis

Lung 12/31/1975

Bone Surface 12/31/1975

Liver 12/31/1975

Adrenals 12/31/1975

Table 12. Example Calculation Bioassay Information.

Date Bioassay Results

Gross Alpha MDA 

(dpm/24 h)

Gross Beta MDA 

(dpm/24 h)

Gross Gamma 

MDA (dpm/24 h)

12/31/1969 <MDA 0.2 2 100

12/31/1970 <MDA 0.2 2 100

12/31/1971 <MDA 0.2 2 100

Table 13. Example Calculation Air Concentration Information.

Highest Annual Alpha Air Concentration for 1967–1971 0.0336 pCi/m3

Highest Annual Beta/Gamma Air Concentration for 1967–1971 4.2 pCi/m3

Unmonitored Period 01/01/1967–12/31/1968

The highest 95th-percentile alpha air concentration for 1967 through 1971 from Table 1 is 

0.0336 pCi/m3

. The highest 95th-percentile beta/gamma air concentration for 1967 through 1971 

from Table 1 is 4.2 pCi/m3

. These values will be used to determine the alpha, beta, and gamma 

annual intake rates based on BZ data in the tables below. This is an overestimating efficiency 

measure for demonstration purposes. All dose calculations based on the 95th-percentile annual 

air concentration are applied a constant distribution. 

Long-Lived (T1/2 >100 days) Internal Dose, January 1, 1969, Through December 31, 1971 

LBNL bioassay monitoring frequencies were typically six months or one year depending on the 

work. Based on these typical monitoring frequencies, a single bioassay result indicates that the 

worker had, at most, one year of internal exposure potential before the date of the bioassay 
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

September 18, 2017

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sample. Based on the above example, the worker has a potential for intakes from January 1, 

1969, through December 31, 1971. 

The results of the bioassay and BZ assessments and comparisons based on the gross bioassay 

methodologies described above are shown in Tables 21a, 21b, 23a, 23b, 24a, and 24b below. 

Table 21a provides the missed doses for the long-lived alpha emitters based on urinalysis, and 

Table 21b provides the limiting doses based on a comparison of the intake rates based on gross 

alpha urinalysis and the intake rates based on BZ data.

Table 23a provides the missed doses for the long-lived beta emitter based on urinalysis, and 

Table 23b provides the limiting doses based on a comparison of the intake rates based on gross 

beta urinalysis and the intake rates based on BZ data.

Table 24a provides the missed doses for the long-lived gamma emitter based on urinalysis, and 

Table 24b provides the limiting doses based on a comparison of the intake rates based on gross 

gamma urinalysis and the intake rates based on BZ data.

Tables 14, 15, and 16 provide the summary information from the above tables for the long-lived 

radionuclide that results in the largest internal doses to the organ of interest based on the 

comparison of the bioassay intake rate to the BZ intake rate. 

Table 14. Alpha Internal Dose Summary (rem), 1969 to 1971.

Organ Radionuclide Dose (rem) Limiting Data

Lung Ac-227 1.17E+01 BZ

Bone Surface Ac-227 2.76E+00 BZ

Liver Ac-227 7.37E-01 BZ

Adrenals Cm-248 6.80E-04 BZ

Table 15. Beta Internal Dose Summary (rem), 1969 to 1971.

Organ Radionuclide Dose (rem) Limiting Data

Lung Ra-228 6.80E-01 BZ

Bone Surface Ra-228 4.15E-01 BZ

Liver Pb-210 7.87E-02 Bioassay

Adrenals Tb-158 6.80E-03 BZ

Table 16. Gamma Internal Dose Summary (rem), 1969 to 1971.

Organ Radionuclide Dose (rem) Limiting Data

Lung Tm-170 1.15E-01 BZ

Bone Surface Hf-172 1.77E-01 BZ

Liver Cd-109 1.09E-02 BZ

Adrenals Hf-172 1.51E-03 BZ
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

September 18, 2017

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Short-Lived (T1/2 <100 days) Internal Dose, January 1, 1969, Through December 31, 1971 

The results of the short-lived internal dose based on BZ assessments described above are shown 

in Tables 22a, 22b, 25a, and 25b below. Tables 22a and 22b provide the radionuclides that yield 

the highest committed doses based on BZ data from the short-lived alpha emitters. Tables 25a 

and 25b provide the radionuclides that yield the highest committed doses based on BZ data from 

the short-lived beta and gamma emitters. A summary of these results is shown in Table 17a. As 

previously indicated, IREP cannot accept a 50-year committed dose as input. Therefore, the 

intake rates for the particular radionuclides are then run using IMBA or CAD to determine the 

annual equivalent doses to the cancer diagnosis date. The comparison values are based on a 

single year of intake regardless of the actual intake period because they are for comparison 

purposes only. Table 17b provides the unmonitored total dose from the start of intake to the date 

of cancer diagnosis for the alpha-, beta-, and gamma-emitting radionuclides listed in Table 17a. 

Table 17a. Short-Lived Internal Committed Dose Summary for Radionuclide 

Selection (rem), 1969 to 1971. 

Organ Emission Type Radionuclide Dose (Rem)

Lung Alpha Th-227 2.14E-02

Bone Surface Alpha Gd-148 2.99E-01

Liver Alpha Gd-148 5.68E-02

Adrenals Alpha Po-208 6.29E-05

Lung Beta Cu-64 2.68E-03

Bone Surface Beta Zr-95 2.39E-03

Liver Beta Ir-192 4.04E-04

Adrenals Beta Na-24 1.77E-04

Lung Gamma Re-186 3.08E-03

Bone Surface Gamma Te-123 8.99E-03

Liver Gamma Hg-194 2.72E-03

Adrenals Gamma Hg-194 3.48E-03

NOTE: Committed doses summarized from Tables 22a, 22b, 25a, and 25b. 

Table 17b. Short-Lived Internal Dose Summary (rem), 1969 to 1971. 

Organ Emission Type Radionuclide Dose (Rem)

Lung Alpha Th-227 6.37E-02

Bone Surface Alpha Gd-148 7.06E-02

Liver Alpha Gd-148 1.29E-02

Adrenals Alpha Po-208 1.88E-04

Lung Beta Cu-64 7.92E-03

Bone Surface Beta Zr-95 7.11E-03

Liver Beta Ir-192 1.25E-03

Adrenals Beta Na-24 5.10E-04

Lung Gamma Re-186 9.22E-03

Bone Surface Gamma Te-123 4.88E-03

Liver Gamma Hg-194 1.88E-03

Adrenals Gamma Hg-194 2.37E-03

NOTE: Doses determined using IMBA or CAD.
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

September 18, 2017

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Final Internal Dose, January 1, 1969, Through December 31, 1971 

Table 18 summarizes the internal doses to be assigned to the organs of interest based on the 

comparison of the bioassay and breathing data for short- and long-lived beta- and gammaemitting radionuclides in Tables 14, 15, 16, and 17b. 

Table 18. Internal Dose Summary (rem), 1969 to 1971. 

Organ Emission Type Intake Assigned Radionuclide Dose (Rem)

Lung Alpha Long-Lived Ac-227 1.17E+01

Lung Alpha Short-Lived Not applicablea Not applicablea

Bone Surface Alpha Long-Lived Ac-227 2.76E+00

Bone Surface Alpha Short-Lived Not applicablea Not applicablea

Liver Alpha Long-Lived Ac-227 7.37E-01

Liver Alpha Short-Lived Not applicablea Not applicablea

Adrenals Alpha Long-Lived Cm-248 6.80E-04

Adrenals Alpha Short-Lived Not applicablea Not applicablea

Lung Beta Long-Lived Ra-228 6.80E-01

Lung Beta Short-Lived Not applicablea Not applicablea

Bone Surface Beta Long-Lived Ra-228 4.15E-01

Bone Surface Beta Short-Lived Not applicablea Not applicablea

Liver Beta Long-Lived Pb-210 7.87E-02

Liver Beta Short-Lived Pb-210 1.25E-03

Adrenals Beta Long-Lived Tb-158 6.80E-03

Adrenals Beta Short-Lived Not applicablea Not applicablea

Lung Gamma Long-Lived Tm-170 1.15E-01

Lung Gamma Short-Lived Not applicablea Not applicablea

Bone Surface Gamma Long-Lived Hf-172 1.77E-01

Bone Surface Gamma Short-Lived Not applicablea Not applicablea

Liver Gamma Long-Lived Cd-109 1.09E-02

Liver Gamma Short-Lived Not applicablea Not applicablea

Adrenals Gamma Long-Lived Not applicableb Not applicableb

Adrenals Gamma Short-Lived Hg-194 2.37E-03

a. Dose from this source term is not applicable as all of the activity associated with the BZ air sampling 

data are associated with the long-lived radionuclide.

b. Dose from this source term is not applicable as all of the activity associated with the BZ air sampling 

data are associated with the short-lived radionuclide.

Unmonitored Worker Internal Dose, January 1, 1967, Through December 31, 1968 

The internal dose for the period from 1967 to 1968 for unmonitored workers is assessed similarly

to the short-lived approach described above, but includes all gross bioassay method 

radionuclides described above. In addition, there are several alpha emitters determined by

separate bioassay methods (Buckley 1969) that are included. These additional alpha emitters are 

not determined by the LBNL gross alpha procedure. Based on LBNL’s bioassay program, if the 

Energy Employee (EE) was monitored for gross alpha activity only, there would be no potential 

for exposure to the separate bioassay method radionuclides of Po-210, Ra-226, and uranium. 

Therefore, these radionuclides were not included in the dose assessment methodology presented 

above. The additional alpha radionuclides are provided in Table 19 below. 
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Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

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Table 19. Additional Alpha Emitters for Unmonitored Workers, 1967 to 1968.

Separate Bioassay Method 

Alpha Radionuclides

Annual Alpha Intake Rate Based 

on BZ Data (dpm/day)

Branching 

Fraction

Po-210 0.50 1

Ra-226 0.49 1

U-232 0.49 1

U-233 0.49 1

U-234 0.49 1

U-235 0.49 1

U-236 0.49 1

U-238 0.49 1

The results of the internal dose to an unmonitored worker based on the BZ assessments in 

Tables 4, 6, 8, 9, and 19 above are shown in Tables 26a, 26b, 27a, and 27b. Tables 26a and 26b 

provides the radionuclides that yield the highest committed doses based on BZ data from the 

alpha emitters. Tables 27a and 27b provides the radionuclides that yield the highest committed 

doses based on BZ data from the beta and gamma emitters. A summary of these results is shown 

in Table 20a. The comparison values are based on a single year of intake regardless of the actual 

intake period because they are for comparison purposes only. Table 20b provides the internal 

doses to an unmonitored worker up to the cancer diagnosis dates for the alpha-, beta-, and 

gamma-emitting radionuclides determined using IMBA or CAD. 

Attachment A provides a detailed discussion of the calculation steps supporting the approach 

discussed above, and the dose results presented in Tables 21a through 27b below.

Table 20a. Unmonitored Worker Internal Committed Dose Summary (rem), 

1967 to 1968. 

Organ Emission Type Radionuclide Dose (Rem)

Lung Alpha Ac-227 4.76E+00

Bone Surface Alpha Ac-227 4.11E+02

Liver Alpha Ac-227 9.31E+01

Adrenals Alpha Ac-227 3.03E-03

Lung Beta Ra-228 2.32E-01

Bone Surface Beta Ra-228 1.35E+00

Liver Beta Pu-241 1.53E-01

Adrenals Beta Tb-158 6.52E-03

Lung Gamma Tm-170 3.84E-02

Bone Surface Gamma Hf-172 6.64E-02

Liver Gamma Cd-109 4.47E-02

Adrenals Gamma Hg-194 3.48E-03

NOTE: Committed doses summarized from Tables 26b and 27b. 
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

September 18, 2017

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Table 20b. Unmonitored Worker Internal Dose Summary (rem), 1967 to 1968. 

Organ Emission Type Radionuclide Dose (Rem)

Lung Alpha Ac-227 8.40E+00

Bone Surface Alpha Ac-227 2.52E+02

Liver Alpha Ac-227 6.60E+01

Adrenals Alpha Ac-227 2.08E-03

Lung Beta Ra-228 4.37E-01

Bone Surface Beta Ra-228 2.21E+01

Liver Beta Pu-241 2.03E-02

Adrenals Beta Tb-158 6.07E-03

Lung Gamma Tm-170 7.70E-02

Bone Surface Gamma Hf-172 1.28E-01

Liver Gamma Cd-109 8.77E-02

Adrenals Gamma Hg-194 1.99E-03

NOTE: Doses determined using IMBA or CAD.

The above example demonstrates the approach for assessing internal dose using bioassay results 

below the MDA and air concentration data at LBNL. Additional guidance is provided below for 

completeness for assessing internal dose using positive bioassay results, and internal dose to an 

unmonitored worker. 

Guidance for Assessing Internal Dose Using Positive Bioassay Results Where the 

Radionuclide is Not Identified

Alpha Radionuclides: 

1. Calculate the fitted dose from long-lived alpha radionuclides. 

a. For each radionuclide, calculate the intake and fitted dose for each solubility type 

based on urinalysis data. 

b. For each radionuclide, select the intake/solubility type combination yielding the 

largest internal dose based on urinalysis data. 

c. Select the radionuclide yielding the largest dose in step 1.b. 

2. Calculate the missed dose from long-lived alpha radionuclides. 

a. Repeat the process used for the alpha emitters. 

3. Dose assignment.

a. Fitted dose is compared to missed dose as appropriate for the case in accordance 

with the internal dose reconstruction guidance in ORAUT (2014). 
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

September 18, 2017

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Beta Radionuclides: 

1. Calculate the fitted dose from long-lived beta radionuclides. 

a. For each radionuclide, calculate the intake and fitted dose for each solubility type 

based on urinalysis data.

b. For each radionuclide, select the intake/solubility type combination yielding the 

largest internal dose based on urinalysis data. 

c. Select the radionuclide yielding the largest dose in step 1.b. 

2. Calculate the missed dose from long-lived beta radionuclides. 

a. Repeat the process used for the beta emitters. 

3. Dose assignment.

a. Fitted dose is compared to missed dose as appropriate for the case in accordance 

with the internal dose reconstruction guidance in ORAUT (2014). 

Gamma Radionuclides: 

1. Calculate the fitted dose from long-lived gamma radionuclides. 

a. For each radionuclide, calculate the intake and fitted dose for each solubility type 

based on urinalysis data. 

b. For each radionuclide, select the intake/solubility type combination yielding the 

largest internal dose based on urinalysis data. 

c. Select the radionuclide yielding the largest dose in step 1.b. 

2. Calculate the missed dose from long-lived gamma radionuclides. 

a. Repeat the process used for the gamma emitters. 

3. Dose assignment.

a. Fitted dose is compared to missed dose as appropriate for the case in accordance 

with the internal dose reconstruction guidance in ORAUT (2014). 
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Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

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with the ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or 

ABRWH (or their technical support and review contractors) positions unless specifically marked as such. This document represents preliminary 

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Guidance for Assessing Internal Dose Using Positive Bioassay Results Where the 

Radionuclide is Identified

Alpha Radionuclides: 

1. Calculate the fitted dose for the alpha radionuclide. 

a. Calculate the intake rate and fitted dose for each solubility type based on 

urinalysis data for the radionuclide. 

b. Select the intake rate/solubility type combination yielding the largest internal dose 

based on urinalysis data for the radionuclide. 

2. Calculate the missed dose from long-lived alpha radionuclides. 

a. Repeat the process used for the alpha emitters. 

3. Dose assignment.

a. Fitted dose is compared to missed dose as appropriate for the case in accordance 

with the internal dose reconstruction guidance in ORAUT (2014). 

Beta Radionuclides: 

1. Calculate the fitted dose for the beta radionuclide. 

a. Calculate the intake rate and fitted dose for each solubility type based on 

urinalysis data for the radionuclide. 

b. Select the intake rate/solubility type combination yielding the largest internal dose 

based on urinalysis data for the radionuclide. 

2. Calculate the missed dose from long-lived beta radionuclides. 

a. Repeat the process used for the beta emitters. 

3. Dose assignment.

a. Fitted dose is compared to missed dose as appropriate for the case in accordance 

with the internal dose reconstruction guidance in ORAUT (2014). 

Gamma Radionuclides: 

1. Calculate the fitted dose for the gamma radionuclide. 
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

September 18, 2017

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ABRWH (or their technical support and review contractors) positions unless specifically marked as such. This document represents preliminary 

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information that is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.

a. Calculate the intake rate and fitted dose for each solubility type based on 

urinalysis data for the radionuclide. 

b. Select the intake rate/solubility type combination yielding the largest internal dose 

based on urinalysis data for the radionuclide. 

2. Calculate the missed dose from long-lived gamma radionuclides. 

a. Repeat the process used for the gamma emitters. 

3. Dose assignment.

a. Fitted dose is compared to missed dose as appropriate for the case in accordance 

with the internal dose reconstruction guidance in ORAUT (2014). 

Assessing Internal Dose to an Unmonitored Worker

The method for assessing internal dose to an unmonitored worker at LBNL is detailed in the 

“Unmonitored Worker Internal Dose, January 1, 1967, through December 31, 1968” section 

above. The following summarizes the steps to assess internal dose to an unmonitored worker at 

LBNL. 

Alpha Radionuclides: 

1. Calculate the dose from both the short-lived and long-lived alpha radionuclides. 

a. For each radionuclide, determine the annual intake based on BZ data.

b. For each radionuclide, select the solubility type that yields the largest DCF for the 

organ. 

c. For each radionuclide, multiply the annual intake by the DCF selected in step 1.b. 

d. Select the radionuclide yielding the largest committed dose. 

e. Determine the internal dose for the annual intake of the radionuclide yielding the 

largest committed dose. 

Beta Radionuclides: 

1. Calculate the dose from both the short-lived and long-lived beta radionuclides. 

a. For each radionuclide, determine the annual intake based on BZ data. 
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

September 18, 2017

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ABRWH (or their technical support and review contractors) positions unless specifically marked as such. This document represents preliminary 

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information that is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.

b. For each radionuclide, select the solubility type that yields the largest DCF for the 

organ. 

c. For each radionuclide, multiply the annual intake by the DCF selected in step 1.b. 

d. Select the radionuclide yielding the largest committed dose. 

e. Determine the internal dose for the annual intake of the radionuclide yielding the 

largest committed dose. 

Gamma Radionuclides: 

1. Calculate the dose from both the short-lived and long-lived beta radionuclides. 

a. For each radionuclide, determine the annual intake based on BZ data. 

b. For each radionuclide, select the solubility type that yields the largest DCF for the 

organ. 

c. For each radionuclide, multiply the annual intake by the DCF selected in step 1.b. 

d. Select the radionuclide yielding the largest committed dose. 

e. Determine the internal dose for the annual intake of the radionuclide yielding the 

largest committed dose. 
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and Gamma Bioassay 

and Air Sampling at the Lawrence Berkeley National Laboratory (Rev. 00)

September 18, 2017

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This document represents preliminary positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any information that 

is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.

Table 21a. Gross Alpha Method. 

Radionuclide

Solubility 

Type

Intake 

Rate 

(dpm/day)

Lung 

Dose 

(rem)

Solubility 

Type

Intake

Rate 

(dpm/day)

Bone 

Surface Dose

(rem)

Solubility 

Type

Intake 

Rate

(dpm/day)

Liver 

Dose 

(rem)

Solubility 

Type

Intake

Rate 

(dpm/day)

Adrenals

Dose 

(rem)

Am-241 M 9.40 3.78E-01 M 9.40 2.65E+00 M 9.40 4.93E-01 M 9.40 2.27E-03

Am-243 M 9.39 3.45E-01 M 9.39 2.56E+00 M 9.39 4.77E-01 M 9.39 2.25E-03

Cf-249 M 22.16 1.04E+00 M 22.16 9.99E+00 M 22.16 9.89E-01 M 22.16 2.53E-04

Cf-250 M 22.91 1.17E+00 M 22.91 9.39E+00 M 22.91 9.32E-01 M 22.91 1.11E-04

Cf-252 M 26.56 1.65E+00 M 26.56 1.25E+01 M 26.56 1.25E+00 M 26.56 2.82E-03

Cm-242 M 18.04 8.15E-01 M 18.04 4.91E-01 M 18.04 1.62E-01 M 18.04 5.49E-04

Cm-243 M 9.59 4.47E-01 M 9.59 2.67E+00 M 9.59 5.06E-01 M 9.59 2.32E-03

Cm-244 M 9.67 4.47E-01 M 9.67 2.58E+00 M 9.67 4.93E-01 M 9.67 2.21E-03

Cm-245 M 9.39 3.58E-01 M 9.39 2.58E+00 M 9.39 4.81E-01 M 9.39 2.22E-03

Cm-246 M 9.39 3.62E-01 M 9.39 2.60E+00 M 9.39 4.87E-01 M 9.39 2.23E-03

Cm-248 M 10.23 6.59E-01 M 10.23 1.03E+01 M 10.23 1.92E+00 M 10.23 1.30E-02

Es-254 M 32.65 1.80E+00 M 32.65 3.56E+00 M 32.65 3.62E-01 M 32.65 2.16E-04

Np-237 M 3.77 1.13E-01 M 3.77 9.17E-01 M 3.77 3.94E-02 M 3.77 6.50E-04

Pa-231 S 103.13 7.93E+00 M 5.35 2.00E+00 S 103.13 4.42E-03 S 103.13 7.45E-05

Pu-236 S 725.95 5.42E+01 S 725.95 5.49E+00 S 725.95 1.04E+00 S 725.95 1.10E-02

Pu-238 S 524.14 4.06E+01 S 524.14 6.76E+00 S 524.14 1.30E+00 S 524.14 1.31E-02

Pu-239 S 518.05 3.57E+01 S 518.05 6.44E+00 S 518.05 1.24E+00 S 518.05 1.25E-02

Pu-240 S 518.11 3.58E+01 S 518.11 6.45E+00 S 518.11 1.24E+00 S 518.11 1.25E-02

Pu-242 S 518.03 3.26E+01 S 518.03 6.12E+00 S 518.03 1.18E+00 S 518.03 1.19E-02

Pu-244 S 518.65 3.02E+01 S 518.65 5.95E+00 S 518.65 1.15E+00 S 518.65 1.42E-02

Th-228 S 448.37 7.65E+00 S 448.37 1.68E+02 S 448.37 3.26E-01 S 448.37 2.46E-02

Th-229 S 305.30 1.02E+01 S 305.30 1.15E+02 S 305.30 5.75E-01 S 305.30 2.59E-02

Th-230 S 305.27 5.45E+00 S 305.27 1.78E+01 M 9.39 4.77E-01 S 305.27 9.12E-03

Th-232 S 305.26 5.09E+00 S 305.26 1.82E+01 S 305.26 9.94E-02 S 305.26 9.12E-03

Ac-227 S 38661.59 1.27E+04 S 38661.59 3.01E+03 S 38661.59 8.01E+02 S 38661.59 1.71E-01

NOTE: Sample method MDA = 0.2 dpm/sample used to determine intake rate and missed dose based on urinalysis (rem).
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and Air Sampling at the Lawrence Berkeley National Laboratory (Rev. 00)

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Table 21b. Gross Alpha Method (Continued). 

Radionuclide

Intake Rate Based 

on BZ Data 

(dpm/day)

Lung 

Dose 

(rem)

Bioassay or 

BZ Data

Bone 

Surface Dose

(rem)

Bioassay or 

BZ Data

Liver 

Dose 

(rem)

Bioassay or 

BZ Data

Adrenals 

Dose 

(rem)

Bioassay or 

BZ Data

Am-241 0.49 1.97E-02 BZ 1.38E-01 BZ 2.57E-02 BZ 1.18E-04 BZ

Am-243 0.49 1.80E-02 BZ 1.34E-01 BZ 2.49E-02 BZ 1.18E-04 BZ

Cf-249 0.49 2.31E-02 BZ 2.21E-01 BZ 2.19E-02 BZ 5.60E-06 BZ

Cf-250 0.49 2.51E-02 BZ 2.01E-01 BZ 2.00E-02 BZ 2.38E-06 BZ

Cf-252 0.51 3.14E-02 BZ 2.39E-01 BZ 2.39E-02 BZ 5.38E-05 BZ

Cm-242 0.50 2.24E-02 BZ 1.35E-02 BZ 4.47E-03 BZ 1.51E-05 BZ

Cm-243 0.49 2.29E-02 BZ 1.37E-01 BZ 2.60E-02 BZ 1.19E-04 BZ

Cm-244 0.49 2.27E-02 BZ 1.31E-01 BZ 2.50E-02 BZ 1.12E-04 BZ

Cm-245 0.49 1.87E-02 BZ 1.35E-01 BZ 2.52E-02 BZ 1.16E-04 BZ

Cm-246 0.49 1.89E-02 BZ 1.36E-01 BZ 2.54E-02 BZ 1.16E-04 BZ

Cm-248 0.53 3.44E-02 BZ 5.40E-01 BZ 1.00E-01 BZ 6.80E-04 BZ

Es-254 0.49 2.72E-02 BZ 5.39E-02 BZ 5.48E-03 BZ 3.26E-06 BZ

Np-237 0.49 1.47E-02 BZ 1.19E-01 BZ 5.12E-03 BZ 8.45E-05 BZ

Pa-231 0.49 3.77E-02 BZ 1.84E-01 BZ 2.10E-05 BZ 3.54E-07 BZ

Pu-236 0.49 3.67E-02 BZ 3.72E-03 BZ 7.05E-04 BZ 7.45E-06 BZ

Pu-238 0.49 3.80E-02 BZ 6.33E-03 BZ 1.22E-03 BZ 1.23E-05 BZ

Pu-239 0.49 3.38E-02 BZ 6.10E-03 BZ 1.17E-03 BZ 1.18E-05 BZ

Pu-240 0.49 3.38E-02 BZ 6.10E-03 BZ 1.18E-03 BZ 1.18E-05 BZ

Pu-242 0.49 3.09E-02 BZ 5.80E-03 BZ 1.12E-03 BZ 1.12E-05 BZ

Pu-244 0.49 2.86E-02 BZ 5.63E-03 BZ 1.09E-03 BZ 1.35E-05 BZ

Th-228 0.49 8.39E-03 BZ 1.85E-01 BZ 3.58E-04 BZ 2.70E-05 BZ

Th-229 0.49 1.65E-02 BZ 1.85E-01 BZ 9.24E-04 BZ 4.17E-05 BZ

Th-230 0.49 8.76E-03 BZ 2.86E-02 BZ 2.49E-02 BZ 1.46E-05 BZ

Th-232 0.49 8.17E-03 BZ 2.92E-02 BZ 1.60E-04 BZ 1.46E-05 BZ

Ac-227 35.55 1.17E+01 BZ 2.76E+00 BZ 7.37E-01 BZ 1.57E-04 BZ

Largest Dose Not applicable 1.17E+01 BZ 2.76E+00 BZ 7.37E-01 BZ 6.80E-04 BZ

Largest 

Radionuclide Not applicable Ac-227 Not applicable Ac-227 Not applicable Ac-227 Not applicable Cm-248 Not applicable

NOTE: Limiting dose based on comparison of the intake rate based on bioassay in Table 21a to the intake rate based on BZ data (rem). 
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and Air Sampling at the Lawrence Berkeley National Laboratory (Rev. 00)

September 18, 2017

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Table 22a. Gross Alpha Method.

Alpha 

Radionuclide

Annual BZ

Intake Rate 

(dpm/day)

Lung

DCFa

Solubility 

Type

Bone 

Surface

DCFa

Solubility

Type

Liver

DCFa

Solubility 

Type

Adrenals

DCFa

Solubility 

Type

Lung

Doseb

Bone 

Surface

Doseb

Liver

Doseb

Adrenals

Doseb

Ac-225 0.60 2.000E-01 S 1.037E-01 F 2.778E-02 F 4.074E-05 F 1.986E-02 1.030E-02 2.758E-03 4.045E-06

Th-227 0.55 2.370E-01 S 1.333E-02 M 7.778E-04 M 4.074E-05 M 2.136E-02 1.202E-03 7.010E-05 3.672E-06

Es-253 0.54 6.296E-02 M 1.037E-02 M 1.000E-03 M 1.222E-06 M 5.619E-03 9.255E-04 8.925E-05 1.091E-07

Sm-146 0.49 1.074E-02 M 7.037E-01 M 1.926E-01 M 8.148E-07 M 8.661E-04 5.675E-02 1.553E-02 6.571E-08

Gd-148 0.49 2.185E-02 M 3.704E+00 F 7.037E-01 F 4.815E-06 F 1.762E-03 2.987E-01 5.675E-02 3.883E-07

Po-208 0.49 6.750E-02 M 4.460E-03 F 1.850E-02 F 7.790E-04 F 5.454E-03 3.604E-04 1.495E-03 6.294E-05

a. ICRP (1995) max organ DCF (mrem/pCi).

b. Committed dose to organ from one year of intake based on BZ data (rem). 

Table 22b. Summary of Table 22a. 

Organ Emission Type

Largest 

Radionuclide

Largest Dose 

(rem)

Lung Alpha Th-227 2.14E-02

Bone Surface Alpha Gd-148 2.99E-01

Liver Alpha Gd-148 5.68E-02

Adrenals Alpha Po-208 6.29E-05
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is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.

Table 23a. Gross Beta Method.

Radionuclide

Solubility 

Type

Intake 

Rate

(dpm/day)

Lung

Dose

(rem)

Solubility 

Type

Intake 

Rate 

(dpm/day)

Bone

Surface

Dose

(rem)

Solubility 

Type

Intake 

Rate 

(dpm/day)

Liver

Dose

(rem)

Solubility 

Type

Intake

Rate 

(dpm/day)

Adrenals 

Dose

(rem)

Ag-110M S 1124.29 7.86E-02 S 1124.29 4.31E-03 S 1124.29 1.44E-02 S 1124.29 1.01E-02

Ca-45 M 15.46 4.51E-04 M 15.46 1.00E-04 M 15.46 6.43E-07 M 15.46 6.43E-07

Cd-113 S 1018.80 8.41E-02 S 1018.80 6.92E-04 S 1018.80 1.91E-02 S 1018.80 6.92E-04

Ce-144 S 89598.00 3.55E+01 S 89598.00 1.89E-01 S 89598.00 5.41E-01 S 89598.00 2.19E-02

Cl-36 M 2.14 1.51E-04 M 2.14 1.52E-06 M 2.14 1.52E-06 M 2.14 1.52E-06

Co-60 S 48.16 7.55E-03 S 48.16 3.70E-04 S 48.16 7.72E-04 S 48.16 8.27E-04

Cs-134 F 2.94 4.57E-05 F 2.94 5.16E-05 F 2.94 5.11E-05 F 2.94 5.39E-05

Cs-137 F 2.62 2.94E-05 F 2.62 3.17E-05 F 2.62 3.13E-05 F 2.62 3.24E-05

Eu-152 M 351.53 2.06E-02 M 351.53 3.85E-02 M 351.53 5.51E-02 M 351.53 9.88E-03

Eu-154 M 100.05 1.08E-02 M 100.05 2.67E-02 M 100.05 2.19E-02 M 100.05 2.80E-03

Ho-166M M 107.00 9.51E-03 M 107.00 2.97E-02 M 107.00 2.52E-02 M 107.00 6.35E-03

Nb-94 S 164.63 3.39E-02 S 164.63 1.08E-03 S 164.63 2.22E-03 S 164.63 2.39E-03

Ni-63 F 4.30 2.76E-06 F 4.30 2.75E-06 F 4.30 2.75E-06 F 4.30 2.75E-06

Os-194 S 303.76 1.61E-01 S 303.76 1.88E-04 S 303.76 1.38E-03 S 303.76 3.07E-04

Pm-147 S 4034.90 1.80E-01 S 4034.90 1.33E-02 S 4034.90 3.56E-03 S 4034.90 2.33E-07

Ru-106 S 63.30 2.99E-02 S 63.30 1.01E-04 S 63.30 1.21E-04 S 63.30 1.29E-04

Sb-125 M 21.04 8.32E-04 M 21.04 1.90E-04 M 21.04 2.81E-05 M 21.04 2.31E-05

Sr-90 F 4.28 4.96E-06 F 4.28 1.51E-03 F 4.28 4.77E-06 F 4.28 4.77E-06

Ta-182 S 2168.20 2.08E-01 S 2168.20 2.40E-03 S 2168.20 3.89E-03 S 2168.20 4.37E-03

Tc-99 M 5.04 2.18E-04 M 5.04 2.82E-07 F 4.53 3.76E-07 M 5.04 2.82E-07

Tl-204 F 4.31 2.73E-06 F 4.31 2.56E-06 F 4.31 2.55E-06 F 4.31 2.55E-06

Tm-170 M 180.16 1.09E-02 M 180.16 2.10E-03 M 180.16 2.84E-04 M 180.16 2.36E-05

Tm-171 M 115.70 6.52E-04 M 115.70 4.35E-03 M 115.70 7.22E-05 M 115.70 6.02E-06

Tb-158 M 509.14 2.75E-02 M 509.14 1.01E-01 M 509.14 4.40E-02 M 509.14 9.37E-03

Ra-228 M 264.82 2.94E+00 M 264.82 1.79E+00 M 264.82 3.95E-02 M 264.82 1.94E-02

Pb-210 F 6.50 2.85E-03 F 6.50 1.86E-01 F 6.50 7.87E-02 F 6.50 2.85E-03

Pu-241 S 5559.11 5.93E-01 S 5559.11 3.64E-01 S 5559.11 7.20E-02 S 5559.11 6.82E-04

NOTE: Sample method MDA = 2 dpm/sample used to determine intake rate and missed dose based on urinalysis (rem).
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September 18, 2017

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is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.

Table 23b. Gross Beta Method (Continued). 

Radionuclide

Intake Rate Based 

on BZ Data 

(dpm/day)

Lung 

Dose 

(rem)

Bioassay or 

BZ Data

Bone

Surface Dose

(rem)

Bioassay or 

BZ Data

Liver 

Dose 

(rem)

Bioassay or 

BZ Data

Adrenals

Dose 

(rem)

Bioassay or 

BZ Data

Ag-110M 62.67 4.38E-03 BZ 2.40E-04 BZ 8.03E-04 BZ 5.63E-04 BZ

Ca-45 62.10 4.51E-04 Bio 1.00E-04 Bio 6.43E-07 Bio 6.43E-07 Bio

Cd-113 61.31 5.06E-03 BZ 4.16E-05 BZ 1.15E-03 BZ 4.16E-05 BZ

Ce-144 61.76 2.44E-02 BZ 1.30E-04 BZ 3.73E-04 BZ 1.51E-05 BZ

Cl-36 62.50 1.51E-04 Bio 1.52E-06 Bio 1.52E-06 Bio 1.52E-06 Bio

Co-60 61.37 7.55E-03 Bio 3.70E-04 Bio 7.72E-04 Bio 8.27E-04 Bio

Cs-134 61.48 4.57E-05 Bio 5.16E-05 Bio 5.11E-05 Bio 5.39E-05 Bio

Cs-137 61.32 2.94E-05 Bio 3.17E-05 Bio 3.13E-05 Bio 3.24E-05 Bio

Eu-152 219.84 1.29E-02 BZ 2.41E-02 BZ 3.45E-02 BZ 6.18E-03 BZ

Eu-154 61.36 6.64E-03 BZ 1.64E-02 BZ 1.34E-02 BZ 1.72E-03 BZ

Ho-166M 61.31 5.45E-03 BZ 1.70E-02 BZ 1.44E-02 BZ 3.64E-03 BZ

Nb-94 61.31 1.26E-02 BZ 4.02E-04 BZ 8.28E-04 BZ 8.92E-04 BZ

Ni-63 61.31 2.76E-06 Bio 2.75E-06 Bio 2.75E-06 Bio 2.75E-06 Bio

Os-194 61.37 3.26E-02 BZ 3.80E-05 BZ 2.80E-04 BZ 6.20E-05 BZ

Pm-147 61.44 2.74E-03 BZ 2.03E-04 BZ 5.42E-05 BZ 3.55E-09 BZ

Ru-106 61.66 2.91E-02 BZ 9.86E-05 BZ 1.18E-04 BZ 1.26E-04 BZ

Sb-125 61.43 8.32E-04 Bio 1.90E-04 Bio 2.81E-05 Bio 2.31E-05 Bio

Sr-90 61.32 4.96E-06 Bio 1.51E-03 Bio 4.77E-06 Bio 4.77E-06 Bio

Ta-182 62.43 6.00E-03 BZ 6.90E-05 BZ 1.12E-04 BZ 1.26E-04 BZ

Tc-99 61.31 2.18E-04 Bio 2.82E-07 Bio 3.76E-07 Bio 2.82E-07 Bio

Tl-204 63.23 2.73E-06 Bio 2.56E-06 Bio 2.55E-06 Bio 2.55E-06 Bio

Tm-170 62.39 3.76E-03 BZ 7.28E-04 BZ 9.84E-05 BZ 8.18E-06 BZ

Tm-171 61.49 3.47E-04 BZ 2.31E-03 BZ 3.84E-05 BZ 3.20E-06 BZ

Tb-158 369.34 1.99E-02 BZ 7.32E-02 BZ 3.19E-02 BZ 6.80E-03 BZ

Ra-228 61.37 6.80E-01 BZ 4.15E-01 BZ 9.15E-03 BZ 4.50E-03 BZ

Pb-210 61.32 2.85E-03 Bio 1.86E-01 Bio 7.87E-02 Bio 2.85E-03 Bio

Pu-241 62.67 4.38E-03 BZ 2.40E-04 BZ 8.03E-04 BZ 5.63E-04 BZ

Largest Dose

Not 

applicable 6.80E-01 BZ 4.15E-01 BZ 7.87E-02 Bio 6.80E-03 BZ

Largest 

Radionuclide

Not 

applicable Ra-228 Not applicable Ra-228 Not applicable Pb-210 Not applicable Tb-158 Not applicable

NOTE: Limiting dose based on comparison of the intake rate based on bioassay in Table 23a to the intake rate based on BZ data (rem). 
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and Gamma Bioassay 

and Air Sampling at the Lawrence Berkeley National Laboratory (Rev. 00)

September 18, 2017

Page 42 of 103

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This document represents preliminary positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any information that 

is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.

Table 24a. Gross Gamma Method.

Radionuclide

Solubility 

Type

Intake 

Rate

(dpm/day)

Lung 

Dose 

(rem)

Solubility 

Type

Intake 

Rate 

(dpm/day)

Bone 

Surface 

Dose 

(rem)

Solubility 

Type

Intake 

Rate 

(dpm/day)

Liver

Dose 

(rem)

Solubility 

Type

Intake 

Rate 

(dpm/day)

Adrenals 

Dose 

(rem)

Ag-108M S 14860.83 1.89E+00 S 14860.83 1.04E-01 S 14860.83 3.07E-01 S 14860.83 2.48E-01

Al-26 M 1493.61 1.65E-01 M 1493.61 1.91E-02 M 1493.61 1.18E-02 M 1493.61 1.40E-02

Au-195 S 8916.33 1.35E-01 S 8916.33 2.61E-03 S 8916.33 2.01E-03 S 8916.33 2.13E-03

Ba-133 F 1269.65 1.40E-03 F 1269.65 1.29E-02 F 1269.65 1.13E-03 F 1269.65 2.47E-03

Bi-207 M 677.52 2.16E-02 M 677.52 8.81E-04 M 677.52 1.57E-03 M 677.52 1.84E-03

Cd-109 S 2900720.02 1.71E+02 S 2900720.02 1.27E+00 S 2900720.02 1.85E+01 S 2900720.02 1.49E+00

Co-57 S 2578.60 1.74E-02 S 2578.60 9.56E-04 S 2578.60 1.12E-03 S 2578.60 1.17E-03

Co-60 S 1204.55 1.89E-01 S 1204.55 9.25E-03 S 1204.55 1.93E-02 S 1204.55 2.07E-02

Cs-134 F 65.95 1.02E-03 F 65.95 1.16E-03 F 65.95 1.15E-03 F 65.95 1.21E-03

Eu-152 M 3113.59 1.82E-01 M 3113.59 3.41E-01 M 3113.59 4.88E-01 M 3113.59 8.75E-02

Eu-154 M 3062.77 3.32E-01 M 3062.77 8.17E-01 M 3062.77 6.70E-01 M 3062.77 8.58E-02

Gd-153 M 12307.76 1.59E-01 M 12307.76 2.36E-01 M 12307.76 6.56E-02 M 12307.76 8.42E-03

Hf-172 M 6623.73 4.94E-01 F 1356.15 1.95E+00 M 6623.73 4.04E-02 M 6623.73 8.16E-02

Mn-54 M 1154.03 6.54E-03 M 1154.03 1.70E-03 M 1154.03 2.98E-03 M 1154.03 2.07E-03

Na-22 F 106.35 2.55E-04 F 106.35 6.06E-04 F 106.35 2.59E-04 F 106.35 3.22E-04

Pm-143 S 1006194.81 6.72E+00 S 1006194.81 6.88E-01 S 1006194.81 1.10E+00 S 1006194.81 1.02E+00

Pm-144 S 129257.06 4.36E+00 S 129257.06 3.95E-01 S 129257.06 8.38E-01 S 129257.06 8.05E-01

Pm-145 S 5326963.91 5.28E+01 S 5326963.91 1.13E+01 S 5326963.91 5.88E+00 S 5326963.91 2.17E+00

Pt-193 F 1676.92 2.47E-05 F 1676.92 2.63E-05 F 1676.92 1.49E-04 F 1676.92 1.85E-04

Rh-101 S 3199.58 1.16E-01 S 3199.58 4.58E-03 S 3199.58 5.90E-03 S 3199.58 6.70E-03

Se-75 M 181.95 1.32E-03 M 181.95 3.90E-04 M 181.95 1.61E-03 M 181.95 6.83E-04

Sm-145 M 84808.59 4.39E-01 M 84808.59 1.82E+00 M 84808.59 7.78E-01 M 84808.59 6.88E-02

Sn-113 M 134610.81 3.07E+00 M 134610.81 1.74E-01 M 134610.81 4.75E-02 M 134610.81 5.74E-02

Ti-44 S 11595.34 6.41E+00 S 11595.34 1.50E-01 S 11595.34 2.36E-01 S 11595.34 2.72E-01

Y-88 S 226248.06 4.16E+00 S 226248.06 4.01E-01 S 226248.06 7.61E-01 S 226248.06 8.32E-01

Zn-65 S 4332.45 5.12E-02 S 4332.45 2.20E-02 S 4332.45 1.85E-02 S 4332.45 2.19E-02

Ag-110M S 17263.39 1.21E+00 S 17263.39 6.62E-02 S 17263.39 2.21E-01 S 17263.39 1.55E-01

Re-184M M 303.12 1.83E-02 M 303.12 2.31E-04 M 303.12 3.13E-04 M 303.12 3.44E-04

Tm-170 M 276050.94 1.66E+01 M 276050.94 3.22E+00 M 276050.94 4.35E-01 M 276050.94 3.62E-02

Te-123M M 613.71 2.48E-02 M 613.71 2.36E-02 M 613.71 1.91E-04 M 613.71 2.92E-04

W-181 F 27057.50 2.73E-04 F 27057.50 3.17E-03 F 27057.50 1.04E-03 F 27057.50 4.92E-04
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and Gamma Bioassay 

and Air Sampling at the Lawrence Berkeley National Laboratory (Rev. 00)

September 18, 2017

Page 43 of 103

This is a working document prepared by NIOSH’s Division of Compensation Analysis and Support (DCAS) or its contractor for use in discussions with the ABRWH or its Working Groups or 

Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions unless specifically marked as such. 

This document represents preliminary positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any information that 

is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.

Radionuclide

Solubility 

Type

Intake 

Rate

(dpm/day)

Lung 

Dose 

(rem)

Solubility 

Type

Intake 

Rate 

(dpm/day)

Bone 

Surface 

Dose 

(rem)

Solubility 

Type

Intake 

Rate 

(dpm/day)

Liver

Dose 

(rem)

Solubility 

Type

Intake 

Rate 

(dpm/day)

Adrenals 

Dose 

(rem)

Tb-158 M 4067.23 2.20E-01 M 4067.23 8.06E-01 M 4067.23 3.52E-01 M 4067.23 7.49E-02

Gd-151 M 50278.30 3.15E-01 M 50278.30 3.42E-01 M 50278.30 9.00E-02 M 50278.30 1.09E-02

NOTE. Sample method MDA = 100 dpm/sample used to determine intake rate and missed dose based on urinalysis (rem).
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and Gamma Bioassay 

and Air Sampling at the Lawrence Berkeley National Laboratory (Rev. 00)

September 18, 2017

Page 44 of 103

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Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions unless specifically marked as such. 

This document represents preliminary positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any information that 

is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.

Table 24b. Gross Gamma Method (Continued).

Radionuclide

Intake Rate Based 

on BZ Data 

(dpm/day)

Lung 

Dose 

(rem)

Bioassay or 

BZ Data

Bone 

Surface 

Dose (rem)

Bioassay or 

BZ Data

Liver 

Dose 

(rem)

Bioassay or 

BZ Data

Adrenals

Dose 

(rem)

Bioassay or 

BZ Data

Ag-108M 21.99 2.80E-03 BZ 1.54E-04 BZ 4.55E-04 BZ 3.67E-04 BZ

Al-26 59.81 6.62E-03 BZ 7.66E-04 BZ 4.74E-04 BZ 5.63E-04 BZ

Au-195 496.47 7.53E-03 BZ 1.45E-04 BZ 1.12E-04 BZ 1.19E-04 BZ

Ba-133 45.07 4.96E-05 BZ 4.56E-04 BZ 4.01E-05 BZ 8.78E-05 BZ

Bi-207 34.08 1.09E-03 BZ 4.43E-05 BZ 7.88E-05 BZ 9.28E-05 BZ

Cd-109 1705.45 1.00E-01 BZ 7.45E-04 BZ 1.09E-02 BZ 8.74E-04 BZ

Co-57 58.50 3.94E-04 BZ 2.17E-05 BZ 2.55E-05 BZ 2.65E-05 BZ

Co-60 30.70 4.81E-03 BZ 2.36E-04 BZ 4.92E-04 BZ 5.27E-04 BZ

Cs-134 27.58 4.28E-04 BZ 4.84E-04 BZ 4.79E-04 BZ 5.06E-04 BZ

Eu-152 38.94 2.28E-03 BZ 4.27E-03 BZ 6.11E-03 BZ 1.09E-03 BZ

Eu-154 37.57 4.07E-03 BZ 1.00E-02 BZ 8.22E-03 BZ 1.05E-03 BZ

Gd-153 115.69 1.50E-03 BZ 2.22E-03 BZ 6.16E-04 BZ 7.92E-05 BZ

Hf-172 122.53 9.14E-03 BZ 1.77E-01 BZ 7.47E-04 BZ 1.51E-03 BZ

Mn-54 61.73 3.50E-04 BZ 9.08E-05 BZ 1.59E-04 BZ 1.11E-04 BZ

Na-22 61.48 1.47E-04 BZ 3.50E-04 BZ 1.50E-04 BZ 1.86E-04 BZ

Pm-143 160.50 1.07E-03 BZ 1.10E-04 BZ 1.75E-04 BZ 1.63E-04 BZ

Pm-144 25.24 8.52E-04 BZ 7.71E-05 BZ 1.64E-04 BZ 1.57E-04 BZ

Pm-145 2170.14 2.15E-02 BZ 4.61E-03 BZ 2.40E-03 BZ 8.82E-04 BZ

Pt-193 290.59 4.28E-06 BZ 4.56E-06 BZ 2.58E-05 BZ 3.20E-05 BZ

Rh-101 43.13 1.56E-03 BZ 6.18E-05 BZ 7.95E-05 BZ 9.03E-05 BZ

Se-75 34.33 2.49E-04 BZ 7.36E-05 BZ 3.05E-04 BZ 1.29E-04 BZ

Sm-145 481.91 2.49E-03 BZ 1.04E-02 BZ 4.42E-03 BZ 3.91E-04 BZ

Sn-113 3374.38 7.69E-02 BZ 4.36E-03 BZ 1.19E-03 BZ 1.44E-03 BZ

Ti-44 33.60 1.86E-02 BZ 4.33E-04 BZ 6.84E-04 BZ 7.87E-04 BZ

Y-88 32.31 5.94E-04 BZ 5.72E-05 BZ 1.09E-04 BZ 1.19E-04 BZ

Zn-65 121.82 1.44E-03 BZ 6.19E-04 BZ 5.20E-04 BZ 6.15E-04 BZ

Ag-110M 19.25 1.35E-03 BZ 7.38E-05 BZ 2.47E-04 BZ 1.73E-04 BZ

Re-184M 70.24 4.23E-03 BZ 5.36E-05 BZ 7.25E-05 BZ 7.97E-05 BZ

Tm-170 1911.87 1.15E-01 BZ 2.23E-02 BZ 3.01E-03 BZ 2.51E-04 BZ

Te-123M 74.04 2.99E-03 BZ 2.85E-03 BZ 2.30E-05 BZ 3.53E-05 BZ

W-181 5603.86 5.65E-05 BZ 6.57E-04 BZ 2.16E-04 BZ 1.02E-04 BZ

Tb-158 59.01 3.19E-03 BZ 1.17E-02 BZ 5.10E-03 BZ 1.09E-03 BZ
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and Gamma Bioassay 

and Air Sampling at the Lawrence Berkeley National Laboratory (Rev. 00)

September 18, 2017

Page 45 of 103

This is a working document prepared by NIOSH’s Division of Compensation Analysis and Support (DCAS) or its contractor for use in discussions with the ABRWH or its Working Groups or 

Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions unless specifically marked as such. 

This document represents preliminary positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any information that 

is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.

Radionuclide

Intake Rate Based 

on BZ Data 

(dpm/day)

Lung 

Dose 

(rem)

Bioassay or 

BZ Data

Bone 

Surface 

Dose (rem)

Bioassay or 

BZ Data

Liver 

Dose 

(rem)

Bioassay or 

BZ Data

Adrenals

Dose 

(rem)

Bioassay or 

BZ Data

Gd-151 388.55 2.43E-03 BZ 2.65E-03 BZ 6.96E-04 BZ 8.45E-05 BZ

Largest 

Dose (rem)

 Not 

applicable 1.15E-01 BZ 1.77E-01 BZ 1.09E-02 BZ 1.51E-03 BZ

Largest 

Radionuclide

Not 

applicable Tm-170 Not applicable Hf-172 Not applicable Cd-109 Not applicable Hf-172 Not applicable

NOTE: Limiting dose based on comparison of the intake rate based on bioassay in Table 24a to the intake rate based on BZ data (rem). 
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and Gamma Bioassay 

and Air Sampling at the Lawrence Berkeley National Laboratory (Rev. 00)

September 18, 2017

Page 46 of 103

This is a working document prepared by NIOSH’s Division of Compensation Analysis and Support (DCAS) or its contractor for use in discussions with the ABRWH or its Working Groups or 

Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions unless specifically marked as such. 

This document represents preliminary positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any information that 

is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.

Table 25a. Gross Beta and Gross Gamma Methods.

Radionuclide

Emission 

Type

Annual BZ 

Intake Rate 

(dpm/day)

Lung 

DCFa / 

Solubility Type

Bone Surface 

DCFa / 

Solubility Type

Liver 

DCFa / 

Solubility Type

Adrenals 

DCFa / 

Solubility Type

Lung Dose 

(rem)b

Bone Surface 

Dose 

(rem)b

Liver Dose 

(rem)b

Adrenals Dose 

(rem)b

Cu-64 Beta 7.99E+03 2.037E-06, S 4.815E-08, F 1.037E-07, F 4.444E-08, F 2.676E-03 6.326E-05 1.362E-04 5.839E-05

Nb-90 Beta 1.87E+03 5.185E-06, S 4.444E-07, M 4.815E-07, M 3.556E-07, M 1.594E-03 1.366E-04 1.480E-04 1.093E-04

Na-24 Beta 1.71E+03 7.037E-07, F 1.111E-06, F 5.556E-07, F 6.296E-07, F 1.975E-04 3.118E-04 1.559E-04 1.767E-04

Zr-97 Beta 1.17E+03 1.037E-05, S 1.630E-06, F 3.259E-07, F 3.519E-07, F 2.002E-03 3.146E-04 6.292E-05 6.793E-05

Pt-197 Beta 9.37E+02 1.704E-07, F 4.815E-08, F 1.741E-07, F 2.185E-07, F 2.624E-05 7.416E-06 2.681E-05 3.366E-05

Ho-166 Beta 3.95E+02 8.519E-06, M 1.444E-07, M 3.111E-07, M 8.519E-09, M 5.526E-04 9.370E-06 2.018E-05 5.526E-07

Os-193 Beta 3.23E+02 8.519E-06, S 1.111E-07, F 9.259E-07, F 1.074E-07, F 4.530E-04 5.909E-06 4.924E-05 5.712E-06

Ce-143 Beta 2.78E+02 1.407E-05, S 2.185E-07, M 6.667E-07, M 5.926E-08, M 6.435E-04 9.991E-06 3.048E-05 2.709E-06

Br-82 Beta 2.52E+02 7.778E-06, M 9.630E-07, F 8.519E-07, M 9.259E-07, M 3.222E-04 3.990E-05 3.529E-05 3.836E-05

Sc-48 Beta 1.92E+02 1.148E-05, S 5.556E-07, S 6.296E-07, S 5.556E-07, S 3.625E-04 1.754E-05 1.988E-05 1.754E-05

Sm-153 Beta 1.78E+02 1.148E-05, M 2.593E-07, M 2.815E-07, M 1.593E-08, M 3.369E-04 7.607E-06 8.259E-06 4.673E-07

Cd-115 Beta 1.56E+02 1.926E-05, S 2.926E-07, F 4.074E-06, F 4.815E-07, F 4.937E-04 7.500E-06 1.044E-04 1.234E-05

Y-90 Beta 1.34E+02 1.889E-05, S 4.074E-07, M 4.074E-07, M 1.481E-08, M 4.152E-04 8.955E-06 8.955E-06 3.256E-07

As-71 Beta 1.32E+02 5.926E-06, M 2.185E-07, M 3.519E-07, M 2.185E-07, M 1.290E-04 4.757E-06 7.660E-06 4.757E-06

Re-186 Beta 1.15E+02 1.852E-05, M 2.111E-07, F 2.667E-07, F 2.037E-07, F 3.499E-04 3.989E-06 5.039E-06 3.849E-06

Np-239 Beta 1.48E+02 1.889E-05, M 1.630E-06, M 1.185E-07, M 4.444E-08, M 4.603E-04 3.971E-05 2.888E-06 1.083E-06

Au-198 Beta 1.33E+02 1.519E-05, S 2.778E-07, F 2.519E-07, F 2.519E-07, F 3.310E-04 6.054E-06 5.489E-06 5.489E-06

Sb-122 Beta 1.36E+02 1.444E-05, M 1.778E-06, F 8.148E-07, F 3.111E-07, F 3.222E-04 3.966E-05 1.818E-05 6.940E-06

Au-199 Beta 1.19E+02 1.778E-05, S 1.222E-07, F 9.630E-08, F 9.630E-08, F 3.475E-04 2.389E-06 1.882E-06 1.882E-06

Yb-175 Beta 1.01E+02 1.593E-05, S 1.185E-06, M 3.296E-08, M 1.407E-08, M 2.637E-04 1.962E-05 5.457E-07 2.330E-07

Lu-177 Beta 8.36E+01 2.704E-05, S 2.741E-06, M 4.074E-08, M 1.778E-08, M 3.715E-04 3.766E-05 5.598E-07 2.443E-07

Tb-161 Beta 8.28E+01 2.593E-05, M 3.185E-06, M 4.444E-07, M 2.185E-08, M 3.531E-04 4.338E-05 6.053E-06 2.976E-07

Ag-111 Beta 8.10E+01 3.407E-05, S 4.074E-07, F 1.296E-05, F 4.074E-07, F 4.540E-04 5.429E-06 1.727E-04 5.429E-06

P-32 Beta 7.09E+01 5.926E-05, M 1.667E-05, F 1.370E-06, F 1.370E-06, F 6.909E-04 1.943E-04 1.598E-05 1.598E-05

Os-191 Beta 7.02E+01 3.704E-05, S 5.556E-07, F 4.444E-06, F 5.185E-07, F 4.273E-04 6.409E-06 5.128E-05 5.982E-06

Rb-86 Beta 6.85E+01 4.074E-06, F 1.481E-05, F 4.074E-06, F 4.074E-06, F 4.591E-05 1.670E-04 4.591E-05 4.591E-05

Th-234 Beta 6.68E+01 1.370E-04, S 1.148E-05, M 1.481E-06, M 1.963E-07, M 1.506E-03 1.262E-04 1.628E-05 2.157E-06

P-33 Beta 6.65E+01 3.556E-05, M 2.778E-06, F 1.963E-07, F 1.963E-07, F 3.890E-04 3.039E-05 2.147E-06 2.147E-06

Pa-233 Beta 6.62E+01 8.519E-05, S 1.185E-05, M 7.407E-07, M 2.667E-07, M 9.274E-04 1.290E-04 8.064E-06 2.903E-06

Ce-141 Beta 6.54E+01 8.889E-05, S 9.630E-06, M 4.444E-06, M 2.370E-07, M 9.552E-04 1.035E-04 4.776E-05 2.547E-06

Nb-95 Beta 6.50E+01 3.000E-05, S 2.667E-06, M 1.815E-06, M 1.222E-06, M 3.208E-04 2.852E-05 1.941E-05 1.307E-05

Ru-103 Beta 6.46E+01 5.556E-05, S 1.593E-06, F 1.556E-06, F 1.593E-06, F 5.904E-04 1.693E-05 1.653E-05 1.693E-05

Hf-181 Beta 6.44E+01 1.037E-04, M 1.778E-04, F 1.333E-06, F 2.667E-06, F 1.098E-03 1.882E-03 1.412E-05 2.823E-05

Fe-59 Beta 6.42E+01 6.296E-05, M 1.111E-05, F 3.259E-05, F 1.111E-05, F 6.650E-04 1.174E-04 3.442E-04 1.174E-04

Hg-203 Beta 6.41E+01 5.185E-05, M 2.407E-06, F 1.963E-06, F 2.333E-06, F 5.465E-04 2.537E-05 2.069E-05 2.459E-05

Sr-89 Beta 6.39E+01 1.407E-04, S 2.519E-05, F 8.148E-07, F 8.148E-07, F 1.478E-03 2.645E-04 8.559E-06 8.559E-06

Y-91 Beta 6.35E+01 1.556E-04, S 8.889E-06, M 8.889E-06, M 1.852E-07, M 1.625E-03 9.284E-05 9.284E-05 1.934E-06

Sb-124 Beta 6.35E+01 1.037E-04, M 2.926E-05, F 5.556E-06, F 3.296E-06, F 1.082E-03 3.053E-04 5.797E-05 3.439E-05
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and Gamma Bioassay 

and Air Sampling at the Lawrence Berkeley National Laboratory (Rev. 00)

September 18, 2017

Page 47 of 103

This is a working document prepared by NIOSH’s Division of Compensation Analysis and Support (DCAS) or its contractor for use in discussions with the ABRWH or its Working Groups or 

Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions unless specifically marked as such. 

This document represents preliminary positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any information that 

is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.

Radionuclide

Emission 

Type

Annual BZ 

Intake Rate 

(dpm/day)

Lung 

DCFa / 

Solubility Type

Bone Surface 

DCFa / 

Solubility Type

Liver 

DCFa / 

Solubility Type

Adrenals 

DCFa / 

Solubility Type

Lung Dose 

(rem)b

Bone Surface 

Dose 

(rem)b

Liver Dose 

(rem)b

Adrenals Dose 

(rem)b

Zr-95 Beta 6.33E+01 1.074E-04, S 2.296E-04, F 3.704E-06, F 8.889E-06, F 1.118E-03 2.391E-03 3.857E-05 9.256E-05

W-188 Beta 6.32E+01 1.148E-07, F 4.074E-06, F 1.926E-06, F 5.926E-08, F 1.193E-06 4.232E-05 2.000E-05 6.155E-07

Tb-160 Beta 6.31E+01 1.222E-04, M 4.074E-05, M 1.519E-05, M 3.704E-06, M 1.268E-03 4.226E-04 1.575E-04 3.842E-05

Ir-192 Beta 6.63E+01 1.259E-04, S 5.185E-06, F 3.704E-05, F 8.519E-06, F 1.372E-03 5.651E-05 4.036E-04 9.283E-05

W-185 Beta 6.30E+01 8.889E-08, F 6.296E-07, F 2.963E-07, F 1.148E-08, F 9.212E-07 6.525E-06 3.071E-06 1.190E-07

Sc-46 Beta 6.28E+01 1.111E-04, S 2.444E-06, S 4.815E-06, S 5.185E-06, S 1.148E-03 2.526E-05 4.975E-05 5.358E-05

S-35 Beta 1.49E+01 3.185E-05, M 1.593E-07, F 1.593E-07, F 1.593E-07, F 7.828E-05 3.914E-07 3.914E-07 3.914E-07

Y-86 Gamma 5.66E+02 2.259E-06, S 3.704E-07, M 4.074E-07, M 3.074E-07, M 2.104E-04 3.449E-05 3.794E-05 2.863E-05

Br-76 Gamma 7.72E+02 4.074E-06, M 6.296E-07, F 5.556E-07, F 5.926E-07, F 5.168E-04 7.987E-05 7.047E-05 7.517E-05

Zr-86 Gamma 1.05E+03 2.481E-06, S 1.185E-06, F 3.519E-07, F 4.444E-07, F 4.271E-04 2.040E-04 6.055E-05 7.649E-05

Co-55 Gamma 8.04E+02 4.444E-06, S 2.407E-07, M 2.741E-07, M 2.148E-07, M 5.872E-04 3.181E-05 3.621E-05 2.838E-05

Rh-100 Gamma 2.91E+02 1.148E-06, S 4.444E-07, F 3.704E-07, F 3.593E-07, F 5.485E-05 2.123E-05 1.770E-05 1.716E-05

Ni-57 Gamma 2.16E+02 4.074E-06, M 3.481E-07, F 3.185E-07, M 2.778E-07, M 1.444E-04 1.234E-05 1.129E-05 9.843E-06

Sb-119 Gamma 1.39E+03 1.185E-07, M 5.556E-07, F 3.148E-08, F 1.111E-08, F 2.714E-05 1.272E-04 7.208E-06 2.544E-06

Au-194 Gamma 1.62E+02 1.593E-06, S 2.852E-07, F 2.111E-07, F 2.074E-07, F 4.246E-05 7.604E-06 5.629E-06 5.530E-06

Am-240 Gamma 1.63E+02 3.704E-06, M 4.074E-06, M 7.037E-07, M 2.333E-07, M 9.910E-05 1.090E-04 1.883E-05 6.243E-06

Br-77 Gamma 1.95E+02 6.296E-07, M 1.815E-07, F 1.593E-07, M 1.741E-07, M 2.021E-05 5.824E-06 5.111E-06 5.587E-06

Ga-67 Gamma 1.34E+02 4.815E-06, M 1.296E-06, F 1.963E-07, F 9.259E-08, F 1.063E-04 2.861E-05 4.333E-06 2.044E-06

Re-186 Gamma 1.01E+03 1.852E-05, M 2.111E-07, F 2.667E-07, F 2.037E-07, F 3.084E-03 3.515E-05 4.440E-05 3.392E-05

Ba-128 Gamma 7.63E+02 2.778E-07, F 2.259E-06, F 2.481E-07, F 2.778E-07, F 3.484E-05 2.833E-04 3.112E-05 3.484E-05

In-111 Gamma 6.93E+01 2.815E-06, M 5.185E-07, F 8.148E-07, F 3.333E-07, F 3.206E-05 5.906E-06 9.280E-06 3.797E-06

Tl-201 Gamma 9.16E+02 1.333E-07, F 2.000E-07, F 1.111E-07, F 1.185E-07, F 2.008E-05 3.012E-05 1.673E-05 1.785E-05

Pd-100 Gamma 8.51E+01 8.519E-06, S 1.185E-06, F 8.148E-06, F 2.185E-06, F 1.192E-04 1.659E-05 1.140E-04 3.058E-05

Mn-52 Gamma 2.96E+01 1.148E-05, M 3.481E-06, F 7.778E-06, F 3.222E-06, F 5.595E-05 1.697E-05 3.790E-05 1.570E-05

Ag-106m Gamma 2.09E+01 6.296E-06, S 2.259E-06, F 1.889E-05, F 5.185E-06, F 2.162E-05 7.759E-06 6.487E-05 1.781E-05

Cs-131 Gamma 9.30E+01 1.148E-07, F 2.407E-07, F 1.037E-07, F 1.074E-07, F 1.756E-06 3.682E-06 1.586E-06 1.643E-06

Ba-131 Gamma 5.82E+01 1.852E-07, F 1.963E-06, F 1.556E-07, F 2.333E-07, F 1.771E-06 1.877E-05 1.488E-06 2.232E-06

Rh-99 Gamma 4.49E+01 1.444E-05, S 1.037E-06, F 8.519E-07, F 8.889E-07, F 1.067E-04 7.659E-06 6.291E-06 6.565E-06

V-48 Gamma 3.34E+01 3.333E-05, M 5.926E-06, F 1.815E-06, M 2.630E-06, F 1.830E-04 3.253E-05 9.963E-06 1.444E-05

Te-121 Gamma 6.94E+01 2.667E-06, M 2.852E-06, F 5.556E-07, M 9.259E-07, F 3.045E-05 3.256E-05 6.343E-06 1.057E-05

Sr-82 Gamma 1.12E+02 1.519E-04, S 3.593E-05, F 2.778E-06, F 3.593E-06, F 2.794E-03 6.611E-04 5.111E-05 6.611E-05

Cr-51 Gamma 6.72E+02 3.259E-07, S 8.519E-08, F 5.185E-08, F 5.556E-08, F 3.603E-05 9.416E-06 5.731E-06 6.141E-06

Yb-169 Gamma 4.49E+01 6.296E-05, S 1.222E-05, M 6.667E-07, M 5.185E-07, M 4.651E-04 9.029E-05 4.925E-06 3.831E-06

Ag-105 Gamma 4.87E+01 9.630E-06, S 1.556E-06, F 1.556E-05, F 3.296E-06, F 7.713E-05 1.246E-05 1.246E-04 2.640E-05

Be-7 Gamma 6.17E+02 4.444E-07, S 8.148E-08, M 8.519E-08, S 1.000E-07, S 4.505E-05 8.259E-06 8.635E-06 1.014E-05

Sr-85 Gamma 6.46E+01 7.778E-06, S 3.444E-06, F 1.000E-06, S 1.778E-06, F 8.260E-05 3.658E-05 1.062E-05 1.888E-05

Hf-175 Gamma 6.73E+01 1.667E-05, M 3.481E-05, F 1.148E-06, F 2.630E-06, F 1.843E-04 3.851E-04 1.270E-05 2.909E-05

Re-183 Gamma 1.18E+02 5.402E-08, M 6.327E-10, M 4.958E-10, M 4.847E-10, M 1.047E-06 1.227E-08 9.612E-09 9.397E-09

Co-58 Gamma 6.28E+01 2.889E-05, S 1.185E-06, M 2.259E-06, M 2.370E-06, S 2.981E-04 1.223E-05 2.331E-05 2.446E-05

Co-56 Gamma 2.52E+01 7.407E-05, S 4.074E-06, M 8.148E-06, M 8.519E-06, S 3.064E-04 1.685E-05 3.371E-05 3.524E-05

Zr-88 Gamma 6.29E+01 3.444E-05, S 5.185E-05, F 8.148E-06, F 2.074E-05, F 3.560E-04 5.359E-04 8.421E-05 2.143E-04

Os-185 Gamma 6.24E+01 1.704E-05, S 4.074E-06, F 1.889E-05, F 7.037E-06, F 1.747E-04 4.178E-05 1.937E-04 7.216E-05
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and Gamma Bioassay 

and Air Sampling at the Lawrence Berkeley National Laboratory (Rev. 00)

September 18, 2017

Page 48 of 103

This is a working document prepared by NIOSH’s Division of Compensation Analysis and Support (DCAS) or its contractor for use in discussions with the ABRWH or its Working Groups or 

Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions unless specifically marked as such. 

This document represents preliminary positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any information that 

is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.

Radionuclide

Emission 

Type

Annual BZ 

Intake Rate 

(dpm/day)

Lung 

DCFa / 

Solubility Type

Bone Surface 

DCFa / 

Solubility Type

Liver 

DCFa / 

Solubility Type

Adrenals 

DCFa / 

Solubility Type

Lung Dose 

(rem)b

Bone Surface 

Dose 

(rem)b

Liver Dose 

(rem)b

Adrenals Dose 

(rem)b

Fe-55 Gamma 2.16E+02 9.630E-07, F 6.667E-06, F 7.778E-06, F 9.630E-07, F 3.417E-05 2.365E-04 2.760E-04 3.417E-05

Hg-194 Gamma 2.49E+02 5.185E-05, F 8.519E-05, F 6.667E-05, F 8.519E-05, F 2.119E-03 3.481E-03 2.724E-03 3.481E-03

Te-123 Gamma 7.77E+01 4.444E-06, M 7.037E-04, F 1.444E-06, F 5.556E-06, F 5.675E-05 8.986E-03 1.844E-05 7.094E-05

a. ICRP (1995) max organ DCF (mrem/pCi).

b. Committed dose to organ from one year of intake based on BZ data (rem).

Table 25b. Summary of Table 25a.

Organ Emission Type

Largest 

Radionuclide

Largest Dose 

(rem)

Lung Beta Cu-64 2.68E-03

Bone Surface Beta Zr-95 2.39E-03

Liver Beta Ir-192 4.04E-04

Adrenals Beta Na-24 1.77E-04

Lung Gamma Re-186 3.08E-03

Bone Surface Gamma Te-123 8.99E-03

Liver Gamma Hg-194 2.72E-03

Adrenals Gamma Hg-194 3.48E-03
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and Gamma Bioassay 

and Air Sampling at the Lawrence Berkeley National Laboratory (Rev. 00)

September 18, 2017

Page 49 of 103

This is a working document prepared by NIOSH’s Division of Compensation Analysis and Support (DCAS) or its contractor for use in discussions with the ABRWH or its Working Groups or 

Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions unless specifically marked as such. 

This document represents preliminary positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any information that 

is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.

Table 26a. Unmonitored Worker Alpha Method. 

Alpha 

Radionuclide

Annual BZ Intake 

Rate (dpm/day) Lung DCFa 

Solubility 

Type

Bone 

Surface

DCFa

Solubility 

Type Liver DCFa

Solubility 

Type

Adrenals

DCFa

Solubility 

Type

Lung Dose

(rem)b

Bone 

Surface

Dose (rem)b

Liver Dose

(rem)b

Adrenals

Dose 

(rem)b

Ac-225 0.60 2.000E-01 S 1.037E-01 F 2.778E-02 F 4.074E-05 F 1.986E-02 1.030E-02 2.758E-03 4.045E-06

Th-227 0.55 2.370E-01 S 1.333E-02 M 7.778E-04 M 4.074E-05 M 2.136E-02 1.202E-03 7.010E-05 3.672E-06

Es-253 0.54 6.296E-02 M 1.037E-02 M 1.000E-03 M 1.222E-06 M 5.619E-03 9.255E-04 8.925E-05 1.091E-07

Sm-146 0.49 1.074E-02 M 7.037E-01 M 1.926E-01 M 8.148E-07 M 8.661E-04 5.675E-02 1.553E-02 6.571E-08

Gd-148 0.49 2.185E-02 M 3.704E+00 F 7.037E-01 F 4.815E-06 F 1.762E-03 2.987E-01 5.675E-02 3.883E-07

Po-208 0.49 6.750E-02 M 4.460E-03 F 1.850E-02 F 7.790E-04 F 5.454E-03 3.604E-04 1.495E-03 6.294E-05

Am-241 0.49 8.889E-02 M 4.074E+00 M 2.481E-01 M 6.667E-03 M 7.168E-03 3.285E-01 2.001E-02 5.376E-04

Am-243 0.49 8.148E-02 M 4.074E+00 M 2.444E-01 M 7.037E-03 M 6.571E-03 3.285E-01 1.971E-02 5.675E-04

Cf-249 0.49 9.630E-02 M 6.296E+00 M 4.444E-01 M 1.222E-04 M 7.765E-03 5.077E-01 3.584E-02 9.856E-06

Cf-250 0.49 1.037E-01 M 2.741E+00 M 2.185E-01 M 2.444E-05 M 8.373E-03 2.213E-01 1.764E-02 1.974E-06

Cf-252 0.51 1.259E-01 M 1.259E+00 M 1.222E-01 M 2.704E-04 M 1.050E-02 1.050E-01 1.019E-02 2.255E-05

Cm-242 0.50 9.259E-02 M 7.037E-02 M 1.852E-02 M 8.889E-05 M 7.564E-03 5.749E-03 1.513E-03 7.262E-06

Cm-243 0.49 1.000E-01 M 2.778E+00 M 2.037E-01 M 4.074E-03 M 8.089E-03 2.247E-01 1.648E-02 3.296E-04

Cm-244 0.49 9.630E-02 M 2.222E+00 M 1.778E-01 M 3.074E-03 M 7.768E-03 1.793E-01 1.434E-02 2.480E-04

Cm-245 0.49 8.519E-02 M 4.074E+00 M 2.481E-01 M 7.037E-03 M 6.869E-03 3.285E-01 2.001E-02 5.675E-04

Cm-246 0.49 8.519E-02 M 4.074E+00 M 2.519E-01 M 7.037E-03 M 6.871E-03 3.286E-01 2.032E-02 5.676E-04

Cm-248 0.53 1.556E-01 M 1.519E+01 M 9.259E-01 M 2.926E-02 M 1.367E-02 1.335E+00 8.139E-02 2.572E-03

Es-254 0.49 1.111E-01 M 3.407E-01 M 3.074E-02 M 1.444E-05 M 9.028E-03 2.769E-02 2.498E-03 1.174E-06

Np-237 0.49 6.296E-02 M 2.481E+00 M 3.704E-02 M 3.185E-03 M 5.077E-03 2.001E-01 2.987E-03 2.569E-04

Pa-231 0.49 2.667E-01 S 1.630E+01 M 1.037E-03 M 4.074E-05 M 2.150E-02 1.314E+00 8.363E-05 3.285E-06

Pu-236 0.49 1.630E-01 S 1.185E+00 M 2.444E-01 M 2.074E-03 M 1.317E-02 9.576E-02 1.975E-02 1.676E-04

Pu-238 0.49 1.889E-01 S 3.370E+00 M 7.037E-01 M 5.926E-03 M 1.523E-02 2.718E-01 5.675E-02 4.779E-04

Pu-239 0.49 1.741E-01 S 3.704E+00 M 7.778E-01 M 6.296E-03 M 1.404E-02 2.987E-01 6.272E-02 5.077E-04

Pu-240 0.49 1.741E-01 S 3.704E+00 M 7.778E-01 M 6.296E-03 M 1.404E-02 2.987E-01 6.272E-02 5.077E-04

Pu-242 0.49 1.593E-01 S 3.556E+00 M 7.407E-01 M 6.296E-03 M 1.284E-02 2.867E-01 5.973E-02 5.077E-04

Pu-244 0.49 1.481E-01 S 3.519E+00 M 7.407E-01 M 6.296E-03 M 1.196E-02 2.841E-01 5.981E-02 5.083E-04

Th-228 0.49 7.778E-01 S 1.037E+00 M 4.444E-02 M 2.852E-03 M 6.291E-02 8.388E-02 3.595E-03 2.307E-04

Th-229 0.49 1.000E+00 S 1.037E+01 M 4.815E-01 M 3.407E-02 M 8.064E-02 8.363E-01 3.883E-02 2.748E-03

Th-230 0.49 1.481E-01 S 5.556E+00 M 7.037E-02 M 5.926E-03 M 1.195E-02 4.480E-01 5.675E-03 4.779E-04

Th-232 0.49 2.852E-01 S 5.556E+00 M 8.519E-02 M 1.630E-02 M 2.300E-02 4.480E-01 6.869E-03 1.314E-03

Ac-227 35.55 8.148E-01 S 7.037E+01 F 1.593E+01 F 5.185E-04 F 4.763E+00 4.113E+02 9.309E+01 3.031E-03

Po-210 0.50 6.296E-02 M 3.481E-03 F 1.444E-02 F 5.926E-04 F 5.154E-03 2.850E-04 1.182E-03 4.851E-05

Ra-226 0.49 6.296E-02 M 3.333E-02 M 4.815E-04 M 1.111E-04 M 5.077E-03 2.688E-03 3.883E-05 8.960E-06

U-232 0.49 5.556E-01 S 3.704E-01 F 3.704E-02 F 8.519E-03 F 4.480E-02 2.987E-02 2.987E-03 6.870E-04

U-233 0.49 1.556E-01 S 4.444E-02 F 5.556E-03 F 1.481E-03 F 1.254E-02 3.584E-03 4.480E-04 1.195E-04

U-234 0.49 1.519E-01 S 4.074E-02 F 5.556E-03 F 1.444E-03 F 1.225E-02 3.285E-03 4.480E-04 1.165E-04

U-235 0.49 1.333E-01 S 4.074E-02 F 5.185E-03 F 1.333E-03 F 1.075E-02 3.285E-03 4.181E-04 1.075E-04
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and Gamma Bioassay 

and Air Sampling at the Lawrence Berkeley National Laboratory (Rev. 00)

September 18, 2017

Page 50 of 103

This is a working document prepared by NIOSH’s Division of Compensation Analysis and Support (DCAS) or its contractor for use in discussions with the ABRWH or its Working Groups or 

Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions unless specifically marked as such. 

This document represents preliminary positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any information that 

is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.

Alpha 

Radionuclide

Annual BZ Intake 

Rate (dpm/day) Lung DCFa 

Solubility 

Type

Bone 

Surface

DCFa

Solubility 

Type Liver DCFa

Solubility 

Type

Adrenals

DCFa

Solubility 

Type

Lung Dose

(rem)b

Bone 

Surface

Dose (rem)b

Liver Dose

(rem)b

Adrenals

Dose 

(rem)b

U-236 0.49 1.370E-01 S 4.074E-02 F 5.185E-03 F 1.333E-03 F 1.105E-02 3.285E-03 4.181E-04 1.075E-04

U-238 0.49 1.259E-01 S 3.704E-02 F 4.815E-03 F 1.259E-03 F 1.015E-02 2.987E-03 3.883E-04 1.015E-04

a. ICRP (1995) max organ DCF (mrem/pCi). 

b. Committed dose to organ from one year of intake based on BZ data (rem)

Table 26b. Summary of Table 26a.

Organ Emission Type

Largest 

Radionuclide

Largest Dose 

(rem)

Lung Alpha Ac-227 4.76E+00

Bone Surface Alpha Ac-227 4.11E+02

Liver Alpha Ac-227 9.31E+01

Adrenals Alpha Ac-227 3.03E-03
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and Gamma Bioassay 

and Air Sampling at the Lawrence Berkeley National Laboratory (Rev. 00)

September 18, 2017

Page 51 of 103

This is a working document prepared by NIOSH’s Division of Compensation Analysis and Support (DCAS) or its contractor for use in discussions with the ABRWH or its Working Groups or 

Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions unless specifically marked as such. 

This document represents preliminary positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any information that 

is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.

Table 27a. Unmonitored Worker Beta and Gamma Methods.

Radionuclide

Emission 

Type

Annual BZ 

Intake Rate 

(dpm/day)

Lung 

DCFa / 

Solubility Type

Bone Surface 

DCFa / 

Solubility Type

Liver 

DCFa / 

Solubility Type

Adrenals 

DCFa / 

Solubility Type

Lung Dose 

(rem)b

Bone Surface 

Dose 

(rem)b

Liver Dose 

(rem)b

Adrenals Dose 

(rem)b

Cu-64 Beta 7.99E+03 2.037E-06, S 4.815E-08, F 1.037E-07, F 4.444E-08, F 2.676E-03 6.326E-05 1.362E-04 5.839E-05

Nb-90 Beta 1.87E+03 5.185E-06, S 4.444E-07, M 4.815E-07, M 3.556E-07, M 1.594E-03 1.366E-04 1.480E-04 1.093E-04

Na-24 Beta 1.71E+03 7.037E-07, F 1.111E-06, F 5.556E-07, F 6.296E-07, F 1.975E-04 3.118E-04 1.559E-04 1.767E-04

Zr-97 Beta 1.17E+03 1.037E-05, S 1.630E-06, F 3.259E-07, F 3.519E-07, F 2.002E-03 3.146E-04 6.292E-05 6.793E-05

Pt-197 Beta 9.37E+02 1.704E-07, F 4.815E-08, F 1.741E-07, F 2.185E-07, F 2.624E-05 7.416E-06 2.681E-05 3.366E-05

Ho-166 Beta 3.95E+02 8.519E-06, M 1.444E-07, M 3.111E-07, M 8.519E-09, M 5.526E-04 9.370E-06 2.018E-05 5.526E-07

Os-193 Beta 3.23E+02 8.519E-06, S 1.111E-07, F 9.259E-07, F 1.074E-07, F 4.530E-04 5.909E-06 4.924E-05 5.712E-06

Ce-143 Beta 2.78E+02 1.407E-05, S 2.185E-07, M 6.667E-07, M 5.926E-08, M 6.435E-04 9.991E-06 3.048E-05 2.709E-06

Br-82 Beta 2.52E+02 7.778E-06, M 9.630E-07, F 8.519E-07, M 9.259E-07, M 3.222E-04 3.990E-05 3.529E-05 3.836E-05

Sc-48 Beta 1.92E+02 1.148E-05, S 5.556E-07, S 6.296E-07, S 5.556E-07, S 3.625E-04 1.754E-05 1.988E-05 1.754E-05

Sm-153 Beta 1.78E+02 1.148E-05, M 2.593E-07, M 2.815E-07, M 1.593E-08, M 3.369E-04 7.607E-06 8.259E-06 4.673E-07

Cd-115 Beta 1.56E+02 1.926E-05, S 2.926E-07, F 4.074E-06, F 4.815E-07, F 4.937E-04 7.500E-06 1.044E-04 1.234E-05

Y-90 Beta 1.34E+02 1.889E-05, S 4.074E-07, M 4.074E-07, M 1.481E-08, M 4.152E-04 8.955E-06 8.955E-06 3.256E-07

As-71 Beta 1.32E+02 5.926E-06, M 2.185E-07, M 3.519E-07, M 2.185E-07, M 1.290E-04 4.757E-06 7.660E-06 4.757E-06

Re-186 Beta 1.15E+02 1.852E-05, M 2.111E-07, F 2.667E-07, F 2.037E-07, F 3.499E-04 3.989E-06 5.039E-06 3.849E-06

Np-239 Beta 1.48E+02 1.889E-05, M 1.630E-06, M 1.185E-07, M 4.444E-08, M 4.603E-04 3.971E-05 2.888E-06 1.083E-06

Au-198 Beta 1.33E+02 1.519E-05, S 2.778E-07, F 2.519E-07, F 2.519E-07, F 3.310E-04 6.054E-06 5.489E-06 5.489E-06

Sb-122 Beta 1.36E+02 1.444E-05, M 1.778E-06, F 8.148E-07, F 3.111E-07, F 3.222E-04 3.966E-05 1.818E-05 6.940E-06

Au-199 Beta 1.19E+02 1.778E-05, S 1.222E-07, F 9.630E-08, F 9.630E-08, F 3.475E-04 2.389E-06 1.882E-06 1.882E-06

Yb-175 Beta 1.01E+02 1.593E-05, S 1.185E-06, M 3.296E-08, M 1.407E-08, M 2.637E-04 1.962E-05 5.457E-07 2.330E-07

Lu-177 Beta 8.36E+01 2.704E-05, S 2.741E-06, M 4.074E-08, M 1.778E-08, M 3.715E-04 3.766E-05 5.598E-07 2.443E-07

Tb-161 Beta 8.28E+01 2.593E-05, M 3.185E-06, M 4.444E-07, M 2.185E-08, M 3.531E-04 4.338E-05 6.053E-06 2.976E-07

Ag-111 Beta 8.10E+01 3.407E-05, S 4.074E-07, F 1.296E-05, F 4.074E-07, F 4.540E-04 5.429E-06 1.727E-04 5.429E-06

P-32 Beta 7.09E+01 5.926E-05, M 1.667E-05, F 1.370E-06, F 1.370E-06, F 6.909E-04 1.943E-04 1.598E-05 1.598E-05

Os-191 Beta 7.02E+01 3.704E-05, S 5.556E-07, F 4.444E-06, F 5.185E-07, F 4.273E-04 6.409E-06 5.128E-05 5.982E-06

Rb-86 Beta 6.85E+01 4.074E-06, F 1.481E-05, F 4.074E-06, F 4.074E-06, F 4.591E-05 1.670E-04 4.591E-05 4.591E-05

Th-234 Beta 6.68E+01 1.370E-04, S 1.148E-05, M 1.481E-06, M 1.963E-07, M 1.506E-03 1.262E-04 1.628E-05 2.157E-06

P-33 Beta 6.65E+01 3.556E-05, M 2.778E-06, F 1.963E-07, F 1.963E-07, F 3.890E-04 3.039E-05 2.147E-06 2.147E-06

Pa-233 Beta 6.62E+01 8.519E-05, S 1.185E-05, M 7.407E-07, M 2.667E-07, M 9.274E-04 1.290E-04 8.064E-06 2.903E-06

Ce-141 Beta 6.54E+01 8.889E-05, S 9.630E-06, M 4.444E-06, M 2.370E-07, M 9.552E-04 1.035E-04 4.776E-05 2.547E-06

Nb-95 Beta 6.50E+01 3.000E-05, S 2.667E-06, M 1.815E-06, M 1.222E-06, M 3.208E-04 2.852E-05 1.941E-05 1.307E-05

Ru-103 Beta 6.46E+01 5.556E-05, S 1.593E-06, F 1.556E-06, F 1.593E-06, F 5.904E-04 1.693E-05 1.653E-05 1.693E-05

Hf-181 Beta 6.44E+01 1.037E-04, M 1.778E-04, F 1.333E-06, F 2.667E-06, F 1.098E-03 1.882E-03 1.412E-05 2.823E-05

Fe-59 Beta 6.42E+01 6.296E-05, M 1.111E-05, F 3.259E-05, F 1.111E-05, F 6.650E-04 1.174E-04 3.442E-04 1.174E-04

Hg-203 Beta 6.41E+01 5.185E-05, M 2.407E-06, F 1.963E-06, F 2.333E-06, F 5.465E-04 2.537E-05 2.069E-05 2.459E-05

Sr-89 Beta 6.39E+01 1.407E-04, S 2.519E-05, F 8.148E-07, F 8.148E-07, F 1.478E-03 2.645E-04 8.559E-06 8.559E-06

Y-91 Beta 6.35E+01 1.556E-04, S 8.889E-06, M 8.889E-06, M 1.852E-07, M 1.625E-03 9.284E-05 9.284E-05 1.934E-06

Sb-124 Beta 6.35E+01 1.037E-04, M 2.926E-05, F 5.556E-06, F 3.296E-06, F 1.082E-03 3.053E-04 5.797E-05 3.439E-05

Zr-95 Beta 6.33E+01 1.074E-04, S 2.296E-04, F 3.704E-06, F 8.889E-06, F 1.118E-03 2.391E-03 3.857E-05 9.256E-05

W-188 Beta 6.32E+01 1.148E-07, F 4.074E-06, F 1.926E-06, F 5.926E-08, F 1.193E-06 4.232E-05 2.000E-05 6.155E-07
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and Gamma Bioassay 

and Air Sampling at the Lawrence Berkeley National Laboratory (Rev. 00)

September 18, 2017

Page 52 of 103

This is a working document prepared by NIOSH’s Division of Compensation Analysis and Support (DCAS) or its contractor for use in discussions with the ABRWH or its Working Groups or 

Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions unless specifically marked as such. 

This document represents preliminary positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any information that 

is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.

Radionuclide

Emission 

Type

Annual BZ 

Intake Rate 

(dpm/day)

Lung 

DCFa / 

Solubility Type

Bone Surface 

DCFa / 

Solubility Type

Liver 

DCFa / 

Solubility Type

Adrenals 

DCFa / 

Solubility Type

Lung Dose 

(rem)b

Bone Surface 

Dose 

(rem)b

Liver Dose 

(rem)b

Adrenals Dose 

(rem)b

Tb-160 Beta 6.31E+01 1.222E-04, M 4.074E-05, M 1.519E-05, M 3.704E-06, M 1.268E-03 4.226E-04 1.575E-04 3.842E-05

Ir-192 Beta 6.63E+01 1.259E-04, S 5.185E-06, F 3.704E-05, F 8.519E-06, F 1.372E-03 5.651E-05 4.036E-04 9.283E-05

W-185 Beta 6.30E+01 8.889E-08, F 6.296E-07, F 2.963E-07, F 1.148E-08, F 9.212E-07 6.525E-06 3.071E-06 1.190E-07

Sc-46 Beta 6.28E+01 1.111E-04, S 2.444E-06, S 4.815E-06, S 5.185E-06, S 1.148E-03 2.526E-05 4.975E-05 5.358E-05

S-35 Beta 1.49E+01 3.185E-05, M 1.593E-07, F 1.593E-07, F 1.593E-07, F 7.828E-05 3.914E-07 3.914E-07 3.914E-07

Ta-182 Beta 6.24E+01 1.963E-04, S 4.815E-06, M 3.630E-06, S 4.074E-06, S 2.015E-03 4.942E-05 3.725E-05 4.182E-05

Tm-170 Beta 6.24E+01 1.222E-04, M 2.370E-05, M 3.185E-06, M 2.667E-07, M 1.254E-03 2.431E-04 3.267E-05 2.735E-06

Ca-45 Beta 6.21E+01 5.926E-05, M 1.037E-05, M 1.185E-07, M 1.185E-07, M 6.050E-04 1.059E-04 1.210E-06 1.210E-06

Ag-110m Beta 6.27E+01 1.407E-04, S 1.407E-05, F 1.556E-04, F 3.630E-05, F 1.450E-03 1.450E-04 1.603E-03 3.740E-04

Ce-144 Beta 6.18E+01 8.148E-04, S 1.259E-04, M 3.704E-04, M 5.185E-06, M 8.274E-03 1.279E-03 3.761E-03 5.265E-05

Bk-249 Beta 6.17E+01 4.074E-05, M 1.519E-02, M 1.037E-03, M 2.889E-07, M 4.133E-04 1.541E-01 1.052E-02 2.931E-06

Ru-106 Beta 6.17E+01 9.630E-04, S 3.111E-05, F 3.111E-05, F 3.148E-05, F 9.762E-03 3.154E-04 3.154E-04 3.191E-04

Tm-171 Beta 6.15E+01 1.148E-05, M 8.519E-05, M 1.407E-06, M 1.185E-07, M 1.161E-04 8.612E-04 1.423E-05 1.198E-06

Cs-134 Beta 6.15E+01 3.148E-05, F 3.556E-05, F 3.519E-05, F 3.704E-05, F 3.182E-04 3.594E-04 3.556E-04 3.744E-04

Pm-147 Beta 6.14E+01 9.259E-05, S 1.889E-04, M 5.185E-05, M 1.185E-09, M 9.354E-04 1.908E-03 5.238E-04 1.197E-08

Sb-125 Beta 6.14E+01 8.148E-05, M 1.000E-04, F 8.519E-06, F 4.444E-06, F 8.230E-04 1.010E-03 8.604E-05 4.489E-05

Tl-204 Beta 6.32E+01 1.296E-06, F 1.185E-06, F 1.185E-06, F 1.185E-06, F 1.348E-05 1.232E-05 1.232E-05 1.232E-05

Co-60 Beta 6.14E+01 3.556E-04, S 1.815E-05, S 3.704E-05, S 4.074E-05, S 3.588E-03 1.831E-04 3.737E-04 4.111E-04

Ra-228 Beta 6.14E+01 2.296E-02, M 1.333E-01, M 5.926E-03, M 5.926E-04, M 2.317E-01 1.345E+00 5.979E-02 5.979E-03

Os-194 Beta 6.14E+01 1.259E-03, S 2.259E-05, F 2.963E-04, F 2.370E-05, F 1.271E-02 2.279E-04 2.990E-03 2.392E-04

Eu-154 Beta 6.14E+01 2.407E-04, M 1.000E-03, M 8.148E-04, M 1.000E-04, M 2.429E-03 1.009E-02 8.220E-03 1.009E-03

Eu-152 Beta 2.20E+02 1.481E-04, M 4.815E-04, M 6.667E-04, M 1.148E-04, M 5.355E-03 1.740E-02 2.410E-02 4.150E-03

Pu-241 Beta 6.13E+01 7.778E-04, S 7.407E-02, M 1.519E-02, M 1.333E-04, M 7.843E-03 7.470E-01 1.531E-01 1.345E-03

Pb-210 Beta 6.13E+01 5.185E-04, F 1.333E-01, F 1.111E-02, F 5.185E-04, F 5.228E-03 1.344E+00 1.120E-01 5.228E-03

Sr-90 Beta 6.13E+01 2.333E-03, S 1.704E-03, F 2.778E-06, F 2.778E-06, F 2.352E-02 1.718E-02 2.801E-05 2.801E-05

Cs-137 Beta 6.13E+01 2.259E-05, F 2.444E-05, F 2.407E-05, F 2.481E-05, F 2.278E-04 2.464E-04 2.427E-04 2.502E-04

Ni-63 Beta 6.13E+01 4.815E-06, M 1.889E-06, F 1.889E-06, F 1.889E-06, F 4.854E-05 1.904E-05 1.904E-05 1.904E-05

Tb-158 Beta 3.69E+02 1.444E-04, M 1.185E-03, M 5.185E-04, M 1.074E-04, M 8.771E-03 7.197E-02 3.149E-02 6.522E-03

Ho-166m Beta 6.13E+01 2.815E-04, M 1.741E-03, M 1.444E-03, M 3.556E-04, M 2.837E-03 1.755E-02 1.456E-02 3.584E-03

Nb-94 Beta 6.13E+01 5.926E-04, S 2.148E-05, S 4.444E-05, S 4.815E-05, S 5.973E-03 2.165E-04 4.480E-04 4.853E-04

Tc-99 Beta 6.13E+01 8.889E-05, M 1.259E-07, F 1.667E-07, F 1.259E-07, F 8.960E-04 1.269E-06 1.680E-06 1.269E-06

Cl-36 Beta 6.25E+01 1.444E-04, M 1.444E-06, F 1.444E-06, F 1.444E-06, F 1.484E-03 1.484E-05 1.484E-05 1.484E-05

Cd-113 Beta 6.13E+01 2.222E-04, S 8.148E-05, F 2.296E-03, F 8.148E-05, F 2.240E-03 8.213E-04 2.315E-02 8.213E-04

Y-86 Gamma 5.66E+02 2.259E-06, S 3.704E-07, M 4.074E-07, M 3.074E-07, M 2.104E-04 3.449E-05 3.794E-05 2.863E-05

Br-76 Gamma 7.72E+02 4.074E-06, M 6.296E-07, F 5.556E-07, F 5.926E-07, F 5.168E-04 7.987E-05 7.047E-05 7.517E-05

Zr-86 Gamma 1.05E+03 2.481E-06, S 1.185E-06, F 3.519E-07, F 4.444E-07, F 4.271E-04 2.040E-04 6.055E-05 7.649E-05

Co-55 Gamma 8.04E+02 4.444E-06, S 2.407E-07, M 2.741E-07, M 2.148E-07, M 5.872E-04 3.181E-05 3.621E-05 2.838E-05

Rh-100 Gamma 2.91E+02 1.148E-06, S 4.444E-07, F 3.704E-07, F 3.593E-07, F 5.485E-05 2.123E-05 1.770E-05 1.716E-05

Ni-57 Gamma 2.16E+02 4.074E-06, M 3.481E-07, F 3.185E-07, M 2.778E-07, M 1.444E-04 1.234E-05 1.129E-05 9.843E-06

Sb-119 Gamma 1.39E+03 1.185E-07, M 5.556E-07, F 3.148E-08, F 1.111E-08, F 2.714E-05 1.272E-04 7.208E-06 2.544E-06

Au-194 Gamma 1.62E+02 1.593E-06, S 2.852E-07, F 2.111E-07, F 2.074E-07, F 4.246E-05 7.604E-06 5.629E-06 5.530E-06
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and Gamma Bioassay 

and Air Sampling at the Lawrence Berkeley National Laboratory (Rev. 00)

September 18, 2017

Page 53 of 103

This is a working document prepared by NIOSH’s Division of Compensation Analysis and Support (DCAS) or its contractor for use in discussions with the ABRWH or its Working Groups or 

Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions unless specifically marked as such. 

This document represents preliminary positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any information that 

is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.

Radionuclide

Emission 

Type

Annual BZ 

Intake Rate 

(dpm/day)

Lung 

DCFa / 

Solubility Type

Bone Surface 

DCFa / 

Solubility Type

Liver 

DCFa / 

Solubility Type

Adrenals 

DCFa / 

Solubility Type

Lung Dose 

(rem)b

Bone Surface 

Dose 

(rem)b

Liver Dose 

(rem)b

Adrenals Dose 

(rem)b

Am-240 Gamma 1.63E+02 3.704E-06, M 4.074E-06, M 7.037E-07, M 2.333E-07, M 9.910E-05 1.090E-04 1.883E-05 6.243E-06

Br-77 Gamma 1.95E+02 6.296E-07, M 1.815E-07, F 1.593E-07, M 1.741E-07, M 2.021E-05 5.824E-06 5.111E-06 5.587E-06

Ga-67 Gamma 1.34E+02 4.815E-06, M 1.296E-06, F 1.963E-07, F 9.259E-08, F 1.063E-04 2.861E-05 4.333E-06 2.044E-06

Re-186 Gamma 1.01E+03 1.852E-05, M 2.111E-07, F 2.667E-07, F 2.037E-07, F 3.084E-03 3.515E-05 4.440E-05 3.392E-05

Ba-128 Gamma 7.63E+02 2.778E-07, F 2.259E-06, F 2.481E-07, F 2.778E-07, F 3.484E-05 2.833E-04 3.112E-05 3.484E-05

In-111 Gamma 6.93E+01 2.815E-06, M 5.185E-07, F 8.148E-07, F 3.333E-07, F 3.206E-05 5.906E-06 9.280E-06 3.797E-06

Tl-201 Gamma 9.16E+02 1.333E-07, F 2.000E-07, F 1.111E-07, F 1.185E-07, F 2.008E-05 3.012E-05 1.673E-05 1.785E-05

Pd-100 Gamma 8.51E+01 8.519E-06, S 1.185E-06, F 8.148E-06, F 2.185E-06, F 1.192E-04 1.659E-05 1.140E-04 3.058E-05

Mn-52 Gamma 2.96E+01 1.148E-05, M 3.481E-06, F 7.778E-06, F 3.222E-06, F 5.595E-05 1.697E-05 3.790E-05 1.570E-05

Ag-106m Gamma 2.09E+01 6.296E-06, S 2.259E-06, F 1.889E-05, F 5.185E-06, F 2.162E-05 7.759E-06 6.487E-05 1.781E-05

Cs-131 Gamma 9.30E+01 1.148E-07, F 2.407E-07, F 1.037E-07, F 1.074E-07, F 1.756E-06 3.682E-06 1.586E-06 1.643E-06

Ba-131 Gamma 5.82E+01 1.852E-07, F 1.963E-06, F 1.556E-07, F 2.333E-07, F 1.771E-06 1.877E-05 1.488E-06 2.232E-06

Rh-99 Gamma 4.49E+01 1.444E-05, S 1.037E-06, F 8.519E-07, F 8.889E-07, F 1.067E-04 7.659E-06 6.291E-06 6.565E-06

V-48 Gamma 3.34E+01 3.333E-05, M 5.926E-06, F 1.815E-06, M 2.630E-06, F 1.830E-04 3.253E-05 9.963E-06 1.444E-05

Te-121 Gamma 6.94E+01 2.667E-06, M 2.852E-06, F 5.556E-07, M 9.259E-07, F 3.045E-05 3.256E-05 6.343E-06 1.057E-05

Sr-82 Gamma 1.12E+02 1.519E-04, S 3.593E-05, F 2.778E-06, F 3.593E-06, F 2.794E-03 6.611E-04 5.111E-05 6.611E-05

Cr-51 Gamma 6.72E+02 3.259E-07, S 8.519E-08, F 5.185E-08, F 5.556E-08, F 3.603E-05 9.416E-06 5.731E-06 6.141E-06

Yb-169 Gamma 4.49E+01 6.296E-05, S 1.222E-05, M 6.667E-07, M 5.185E-07, M 4.651E-04 9.029E-05 4.925E-06 3.831E-06

Ag-105 Gamma 4.87E+01 9.630E-06, S 1.556E-06, F 1.556E-05, F 3.296E-06, F 7.713E-05 1.246E-05 1.246E-04 2.640E-05

Be-7 Gamma 6.17E+02 4.444E-07, S 8.148E-08, M 8.519E-08, S 1.000E-07, S 4.505E-05 8.259E-06 8.635E-06 1.014E-05

Sr-85 Gamma 6.46E+01 7.778E-06, S 3.444E-06, F 1.000E-06, S 1.778E-06, F 8.260E-05 3.658E-05 1.062E-05 1.888E-05

Hf-175 Gamma 6.73E+01 1.667E-05, M 3.481E-05, F 1.148E-06, F 2.630E-06, F 1.843E-04 3.851E-04 1.270E-05 2.909E-05

Re-183 Gamma 1.18E+02 5.402E-08, M 6.327E-10, M 4.958E-10, M 4.847E-10, M 1.047E-06 1.227E-08 9.612E-09 9.397E-09

Co-58 Gamma 6.28E+01 2.889E-05, S 1.185E-06, M 2.259E-06, M 2.370E-06, S 2.981E-04 1.223E-05 2.331E-05 2.446E-05

Co-56 Gamma 2.52E+01 7.407E-05, S 4.074E-06, M 8.148E-06, M 8.519E-06, S 3.064E-04 1.685E-05 3.371E-05 3.524E-05

Zr-88 Gamma 6.29E+01 3.444E-05, S 5.185E-05, F 8.148E-06, F 2.074E-05, F 3.560E-04 5.359E-04 8.421E-05 2.143E-04

Os-185 Gamma 6.24E+01 1.704E-05, S 4.074E-06, F 1.889E-05, F 7.037E-06, F 1.747E-04 4.178E-05 1.937E-04 7.216E-05

Fe-55 Gamma 2.16E+02 9.630E-07, F 6.667E-06, F 7.778E-06, F 9.630E-07, F 3.417E-05 2.365E-04 2.760E-04 3.417E-05

Hg-194 Gamma 2.49E+02 5.185E-05, F 8.519E-05, F 6.667E-05, F 8.519E-05, F 2.119E-03 3.481E-03 2.724E-03 3.481E-03

Te-123 Gamma 7.77E+01 4.444E-06, M 7.037E-04, F 1.444E-06, F 5.556E-06, F 5.675E-05 8.986E-03 1.844E-05 7.094E-05

Y-88 Gamma 3.23E+01 3.704E-05, S 1.074E-05, M 1.704E-05, M 1.074E-05, M 1.967E-04 5.705E-05 9.050E-05 5.705E-05

Sn-113 Gamma 3.37E+03 4.815E-05, M 1.222E-05, F 1.148E-06, F 1.593E-06, F 2.671E-02 6.781E-03 6.370E-04 8.836E-04

Te-123m Gamma 7.40E+01 8.148E-05, M 1.556E-04, F 6.667E-07, F 1.296E-06, F 9.920E-04 1.894E-03 8.116E-06 1.578E-05

Se-75 Gamma 3.43E+01 1.481E-05, M 4.444E-06, F 2.037E-05, F 8.148E-06, F 8.363E-05 2.509E-05 1.150E-04 4.599E-05

W-181 Gamma 5.60E+03 2.037E-08, F 2.370E-07, F 7.778E-08, F 3.704E-08, F 1.877E-05 2.184E-04 7.166E-05 3.412E-05

Tm-170 Gamma 1.91E+03 1.222E-04, M 2.370E-05, M 3.185E-06, M 2.667E-07, M 3.842E-02 7.451E-03 1.001E-03 8.382E-05

Re-184m Gamma 7.02E+01 1.222E-04, M 1.556E-06, M 2.111E-06, M 2.296E-06, M 1.411E-03 1.796E-05 2.438E-05 2.652E-05

Au-195 Gamma 4.96E+02 3.074E-05, S 5.926E-07, S 4.444E-07, S 4.815E-07, S 2.509E-03 4.837E-05 3.628E-05 3.930E-05

Gd-153 Gamma 1.16E+02 2.630E-05, M 2.111E-04, F 5.556E-05, F 5.926E-06, F 5.002E-04 4.016E-03 1.057E-03 1.127E-04

Zn-65 Gamma 1.22E+02 2.407E-05, S 1.037E-05, S 8.519E-06, S 1.037E-05, S 4.822E-04 2.077E-04 1.706E-04 2.077E-04

Ag-110m Gamma 1.92E+01 1.407E-04, S 1.407E-05, F 1.556E-04, F 3.630E-05, F 4.454E-04 4.454E-05 4.922E-04 1.149E-04
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and Gamma Bioassay 

and Air Sampling at the Lawrence Berkeley National Laboratory (Rev. 00)

September 18, 2017

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Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions unless specifically marked as such. 

This document represents preliminary positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any information that 

is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.

Radionuclide

Emission 

Type

Annual BZ 

Intake Rate 

(dpm/day)

Lung 

DCFa / 

Solubility Type

Bone Surface 

DCFa / 

Solubility Type

Liver 

DCFa / 

Solubility Type

Adrenals 

DCFa / 

Solubility Type

Lung Dose 

(rem)b

Bone Surface 

Dose 

(rem)b

Liver Dose 

(rem)b

Adrenals Dose 

(rem)b

Pm-143 Gamma 1.60E+02 1.370E-05, S 1.000E-05, M 1.630E-05, M 4.444E-06, M 3.616E-04 2.639E-04 4.300E-04 1.173E-04

Co-57 Gamma 5.85E+01 1.370E-05, S 7.407E-07, S 8.889E-07, S 9.259E-07, S 1.318E-04 7.125E-06 8.550E-06 8.906E-06

Mn-54 Gamma 6.17E+01 1.148E-05, M 6.296E-06, F 1.074E-05, F 4.815E-06, F 1.165E-04 6.390E-05 1.090E-04 4.887E-05

Sm-145 Gamma 4.82E+02 1.074E-05, M 4.815E-05, M 2.111E-05, M 1.815E-06, M 8.510E-04 3.815E-03 1.673E-03 1.438E-04

Pm-144 Gamma 2.52E+01 7.037E-05, S 2.815E-05, M 9.630E-05, M 2.963E-05, M 2.920E-04 1.168E-04 3.996E-04 1.230E-04

Cd-109 Gamma 1.71E+03 1.222E-04, S 8.519E-06, F 1.593E-04, F 1.074E-05, F 3.427E-02 2.389E-03 4.466E-02 3.012E-03

Hf-172 Gamma 1.23E+02 1.519E-04, M 3.296E-03, F 4.074E-05, F 1.074E-04, F 3.059E-03 6.640E-02 8.207E-04 2.164E-03

Cs-134 Gamma 2.76E+01 3.148E-05, F 3.556E-05, F 3.519E-05, F 3.704E-05, F 1.428E-04 1.612E-04 1.596E-04 1.680E-04

Na-22 Gamma 6.15E+01 4.815E-06, F 1.148E-05, F 4.815E-06, F 6.296E-06, F 4.867E-05 1.161E-04 4.867E-05 6.364E-05

Gd-151 Gamma 3.89E+02 1.259E-05, M 8.148E-05, F 2.111E-05, F 1.778E-06, F 8.044E-04 5.205E-03 1.349E-03 1.136E-04

Rh-101 Gamma 4.31E+01 7.778E-05, S 8.148E-06, F 5.926E-06, F 6.296E-06, F 5.515E-04 5.778E-05 4.202E-05 4.465E-05

Co-60 Gamma 3.07E+01 3.556E-04, S 1.815E-05, S 3.704E-05, S 4.074E-05, S 1.795E-03 9.161E-05 1.870E-04 2.057E-04

Eu-154 Gamma 3.76E+01 2.407E-04, M 1.000E-03, M 8.148E-04, M 1.000E-04, M 1.487E-03 6.177E-03 5.033E-03 6.177E-04

Ba-133 Gamma 4.51E+01 3.704E-06, F 3.556E-05, F 2.963E-06, F 6.296E-06, F 2.745E-05 2.635E-04 2.196E-05 4.666E-05

Eu-152 Gamma 3.89E+01 1.481E-04, M 4.815E-04, M 6.667E-04, M 1.148E-04, M 9.486E-04 3.083E-03 4.268E-03 7.351E-04

Pm-145 Gamma 2.17E+03 2.630E-05, S 1.519E-04, M 6.667E-05, M 5.556E-06, M 9.383E-03 5.418E-02 2.379E-02 1.982E-03

Bi-207 Gamma 3.41E+01 6.667E-05, M 2.630E-06, M 4.815E-06, M 5.556E-06, M 3.736E-04 1.474E-05 2.698E-05 3.113E-05

Ti-44 Gamma 3.36E+01 1.593E-03, S 2.889E-04, F 2.667E-04, F 2.815E-04, F 8.797E-03 1.596E-03 1.473E-03 1.555E-03

Pt-193 Gamma 2.91E+02 3.000E-08, F 3.185E-08, F 1.815E-07, F 2.222E-07, F 1.433E-06 1.522E-06 8.671E-06 1.062E-05

Ag-108m Gamma 2.20E+01 4.074E-04, S 2.222E-05, S 1.852E-04, F 5.185E-05, S 1.473E-03 8.035E-05 6.696E-04 1.875E-04

Tb-158 Gamma 5.90E+01 1.444E-04, M 1.185E-03, M 5.185E-04, M 1.074E-04, M 1.401E-03 1.150E-02 5.031E-03 1.042E-03

Al-26 Gamma 5.98E+01 2.259E-04, M 9.630E-05, F 3.704E-05, F 4.444E-05, F 2.222E-03 9.470E-04 3.642E-04 4.371E-04

a. ICRP (1995) max organ DCF (mrem/pCi).

b. Committed dose to organ from one year of intake based on BZ data (rem).

Table 27b. Summary of Table 27a.

Organ Emission Type

Largest 

Radionuclide

Largest Dose 

(rem)

Lung Beta Ra-228 2.32E-01

Bone Surface Beta Ra-228 1.35E+00

Liver Beta Pu-241 1.53E-01

Adrenals Beta Tb-158 6.52E-03

Lung Gamma Tm-170 3.84E-02

Bone Surface Gamma Hf-172 6.64E-02

Liver Gamma Cd-109 4.47E-02

Adrenals Gamma Hg-194 3.48E-03
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

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with the ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or 

ABRWH (or their technical support and review contractors) positions unless specifically marked as such. This document represents preliminary 

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REFERENCES

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White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

 September 18,2017

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with the ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or 

ABRWH (or their technical support and review contractors) positions unless specifically marked as such. This document represents preliminary 

positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any 

information that is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.

LBL (Lawrence Berkeley Laboratory), 1981b, The Environmental Health and Safety Department 

Operational Guide for the Health and Safety Representative, University of California, 

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White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

 September 18,2017

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with the ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or 

ABRWH (or their technical support and review contractors) positions unless specifically marked as such. This document represents preliminary 

positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any 

information that is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.

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137944] 
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

 September 18,2017

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This is a working document prepared by NIOSH’s Division of Compensation Analysis and Support (DCAS) or its contractor for use in discussions 

with the ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or 

ABRWH (or their technical support and review contractors) positions unless specifically marked as such. This document represents preliminary 

positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any 

information that is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.

LRL-B (Lawrence Radiation Laboratory Berkeley), 1980, ARIES Air Sample Summary Data, 

December 1980, University of California, Berkeley, California. [SRDB Ref ID: 137907] 

LRL-B (Lawrence Radiation Laboratory Berkeley), 1981, ARIES Air Sample Summary Data, 

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June 1985, University of California, Berkeley, California. [SRDB Ref ID: 139963] 

National Bureau of Standards (NBS), National Council on Radiation Protection and 

Measurements, 1959, revised 1963, Maximum Permissible Concentrations of 

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ORAUT (Oak Ridge Associated Universities Team), 2010, Site Profile for the Lawrence 

Berkeley National Laboratory, Rev. 2, ORAUT-TKBS-0049, May 10. [SRDB Ref ID: 

81254] 

ORAUT (Oak Ridge Associated Universities Team), 2014, Internal Dose Reconstruction, Rev. 

1, ORAUT-OTIB-0060, September 8. [SRDB Ref ID: 135808] 

ORAUT (Oak Ridge Associated Universities Team), 2017a, 

LBNL_Concept_DR_Dose_Estimates_01-27-2017, Rev. 1.xlsx spreadsheet, Oak Ridge, 

Tennessee, January 27. [SRDB Ref ID: 166606] 

ORAUT (Oak Ridge Associated Universities Team), 2017b, LBNL Annual Average Air 

Concentration Dataset, Rev. 1, Oak Ridge, Tennessee, April 27. [SRDB Ref ID: 

166607] 

Patterson, H. W., 1957, Air Sample Data April 8–10, 1955, May 23. [SRDB Ref ID: 137825] 

Peck, J. S., 1964, Manual of Instructions, Automatic Processing of Airborne Activity Data, JSP777-62, University of California, Berkeley, California, January 24. [SRDB Ref ID: 

137854] 
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

 September 18,2017

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This is a working document prepared by NIOSH’s Division of Compensation Analysis and Support (DCAS) or its contractor for use in discussions 

with the ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or 

ABRWH (or their technical support and review contractors) positions unless specifically marked as such. This document represents preliminary 

positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any 

information that is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.

Schmidt, C. T., T. W. Sargent, D. J. Yeager, and A. G. Low-Beer, 1973, Report of the Bioassay 

Laboratory, July 1972 through June 1973, LBL-2448, November. [SRDB Ref ID: 

71780] 

Schoonover, M., 1994, Workplace Air Sampling Data, memorandum to T. Davis, Lawrence 

Berkeley Laboratory, University of California, Berkeley, California, July 20. [SRDB Ref 

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attachments, University of California, Berkeley, California, March 22. [SRDB Ref ID: 

20908] 

Thaxter, M., 1953, Sampling Methods and Requirements for Estimating Airborne 

Radioparticulate Hazards, MDT-20-53, January 19. [SRDB Ref ID: 21357] 

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21403, p. 5] 

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Procedures for Radioisotope Safety, UCRL-11700, Berkeley, California, October 13. 

[SRDB Ref ID: 21531] 
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

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ABRWH (or their technical support and review contractors) positions unless specifically marked as such. This document represents preliminary 

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information that is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.

ATTACHMENT A

Overview

The following provides a detailed discussion of the calculation steps supporting the results 

presented in Tables 19 through 27 above for assessing gross alpha, gross beta, gross gamma 

bioassay, and alpha and beta/gamma air sampling results. This is presented in Gross Alpha/Beta, 

Gross Gamma Bioassay, Alpha and Beta/Gamma Air Sampling Results Spreadsheets (ORAUT 

2017a). 

As indicated above, the example is for missed dose for an unknown work location and doses to 

several organs of interest with the details listed below:

Table A-1. Example Calculation Employment Information. 

Employment Period 01/01/1967–12/31/1971

Work Location Unknown

Internal Monitored Period 01/01/1969–12/31/1971

Table A-2. Example Calculation Cancer Information. 

Cancer Date of Diagnosis

Lung 12/31/1975

Bone Surface 12/31/1975

Liver 12/31/1975

Adrenals 12/31/1975

Table A-3. Example Calculation Bioassay Information. 

Date Bioassay Results

Gross Alpha MDA 

(dpm/24 h)

Gross Beta MDA 

(dpm/24 h)

Gross Gamma 

MDA (dpm/24 h)

12/31/1969 <MDA 0.2 2 100

12/31/1970 <MDA 0.2 2 100

12/31/1971 <MDA 0.2 2 100

Table A-4. Example Calculation Air Concentration Information. 

Highest Annual Alpha Air Concentration for 1967–1971 0.0336 pCi/m3

Highest Annual Beta/Gamma Air Concentration for 1967–1971 4.2 pCi/m3

Unmonitored Period 01/01/1967–12/31/1968

The following describes the general approach for determining the internal dose from the shortlived and long-lived radionuclides. Refer to Worksheet Descriptions and Example Calculations

for detail in determining the doses.

The list of alpha, beta, and gamma emitters are presented in Tables 3, 5, 7, and 9 above. 
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

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with the ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or 

ABRWH (or their technical support and review contractors) positions unless specifically marked as such. This document represents preliminary 

positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any 

information that is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.

Radionuclides with Half-Lives Less than 100 Days 

Radionuclides with half-lives less than 100 days were considered to be unmonitored, given the 

typical LBNL bioassay frequencies of one year or six months. These are presented in Table 9 

above. The internal doses from these unmonitored radionuclides were assessed based on the 

following: 

1. The LBNL 95th-percentile annual average air concentrations were determined based on a 

statistical reduction of the LBNL Dual Data Entry Phase I and II BZ data effort.

2. The 95th-percentile annual average air concentrations were converted to an annual intake 

rate for each radionuclide and adjusted for the following: 

a. Decay-corrected back 72 hours. 

b. An annual breathing rate of 2,400 m3/yr.

c. Branching fraction (alpha and beta emitters).

d. Gamma yield (gamma emitters).

3. The committed dose for each radionuclide from one year of intake was determined by 

multiplying the annual intake by the highest ICRP (1995) inhalation organ DCF for each 

organ of interest. This is an efficiency measure used to determine the radionuclide 

yielding the highest dose. 

4. Since the IREP input cannot accept a 50-year committed dose, the intake rate for that 

particular radionuclide and given bioassay method (i.e., gross alpha, gross beta, or gross 

gamma) is then run using IMBA or CAD to determine the annual equivalent internal 

doses out to the cancer diagnosis date. 

Radionuclides with Half-Lives Greater than 100 Days 

Radionuclides whose half-lives are greater than 100 days were assessed using bioassay results. 

These are presented in Tables 3, 5, and 7 above. The internal doses based on bioassay results 

from these monitored radionuclides were assessed based on the following: 

1. An intake rate for the assumed internally monitored period of January 1, 1969, through 

December 31, 1971, was calculated using IMBA, based on a urine bioassay result of 

1 dpm/24 hours on December 31, 1971. 

2. The internal dose for each radionuclide based on the calculated intake rate and a cancer 

diagnosis date of December 31, 1975, was determined using IMBA.
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Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

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ABRWH (or their technical support and review contractors) positions unless specifically marked as such. This document represents preliminary 

positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any 

information that is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.

3. The solubility types yielding the largest internal dose to the organ of interest for each 

radionuclide were compiled. 

4. The doses for each radionuclide were converted to missed dose based on the following: 

a. Alpha emitters were adjusted for the sample-specific MDA and their branching 

fraction.

b. Beta emitters were adjusted for the sample-specific MDA and their branching 

fraction.

c. Gamma emitters were adjusted for the sample-specific MDA and their photon yield 

(gammas/disintegration).

5. The intake rates calculated from bioassay data for each radionuclide were compared to 

the intake rates determined from the BZ air monitoring data. The more limiting intake 

rate between the bioassay and BZ data was used to calculate the dose to the organ of 

interest.

6. The radionuclide yielding the highest internal dose to the organ of interest for the given 

bioassay method (i.e., gross alpha, gross beta, or gross gamma) was assigned for each 

year the worker was monitored for intakes. 

Input Sources

Intake rates: IMBA was used to determine the intake rate for each solubility 

type of the radionuclides with T1/2 >100 days, based on 

monitoring from January 1, 1969, to December 31, 1971, and an 

assumed urine sample result of 1 dpm/24 hours on December 31, 

1971.

Dose: IMBA was used to determine the internal dose for each 

radionuclide based on the intake rates derived above and a cancer 

diagnosis date of December 31, 1975. 

Branching Fractions: Rad Toolbox 

Photon Yield Data: Rad Toolbox 

ICRP (1995) Inhalation DCFs: Rad Toolbox 

BZ data: 95th-percentile annual air concentrations were determined based 

on a statistical reduction of the LBNL Dual Data Entry Phase I 

and II BZ data effort.
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

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with the ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or 

ABRWH (or their technical support and review contractors) positions unless specifically marked as such. This document represents preliminary 

positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any 

information that is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.

Worksheet Descriptions

The following describes the various worksheets, along with the detailed methodology for the key 

data in the worksheets: 

Breathing Zone Data

1. This worksheet contains the LBNL 95th-percentile annual average air concentrations 

which were determined based on a statistical reduction of the LBNL Dual Data Entry 

Phase I and II BZ data effort. These data are presented in Table 1 above. 

2. These data were used to determine the annual intake rates for each radionuclide in the 

“Alpha Breathing Zone Int Rates” and “BG Breathing Zone Intake Rates” worksheets. 

3. These data were used to determine the annual intake rate for each radionuclide in the 

“Unmonitored Alpha Organ Doses” and “Unmonitored BG Organ Doses” worksheets. 

Doses Based on Bioassay 

1. This worksheet contains the intake rates and doses for the solubility type yielding the 

highest dose to the organ of interest based on a 1 dpm/24 hour urine sample on 

December 31, 1971, intake from January 1, 1969, to December 31, 1971, and a cancer 

diagnosis date of December 31, 1975. 

2. These intake rates and doses are referenced in the “Gross Alpha Bio Organ Doses,” 

“Gross Beta Bioassay Organ Doses,” and “Gross Gamma Bio Organ Doses” worksheets. 

ICRP 68 DCFs

1. The ICRP (1995) Inhalation DCFs were taken from Rad Toolbox. This includes 

additional radionuclides not used in the “DR Methodology.” 

2. The DCFs are referenced in the “Unmonitored Alpha Organ Doses” and “Unmonitored 

BG Organ Doses” worksheets for the specific radionuclides assessed. They reflect the 

solubility type and DCF yielding the largest dose to the organs assessed. These DCFs are 

used in Tables 22a, 22b, 25a, 25b, 26a, 26b, 27a, and 27b above. 

Alpha Breathing Zone Int Rates

1. This worksheet determines the annual intake rates based on the alpha air concentration 

data from the “Breathing Zone Data” worksheet. These intake rates are is used in Tables 

21b, 22a, 22b, 26a, and 26b above. 

2. Columns D through I contain the decay data which are taken from Rad ToolBox. 
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

 September 18,2017

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3. The decay data in columns D through I is referenced in the “Gross Alpha Bio Organ 

Doses” worksheet.

4. Column C determines the intake rates based on the highest 95th-percentile alpha annual 

air concentration of 0.0336 pCi/m3 for 1967 to 1971 from the “Breathing Zone Data” 

worksheet decay-corrected back 72 hours, adjusted for an annual breathing rate of 

2,400 m3

/year, and adjusted for alpha branching fraction in column H. 

The annual intake rate based on BZ data (dpm/day) in column C is determined by the 

following methods: 

Annual intake rate = Annual air concentration × 2.22 × 2,400 ÷ 365 ÷ Decay 

correction factor ÷ Branching fraction 

Where:

Annual intake rate = annual intake rate based on BZ data (dpm/day) [column C] 

Annual air concentration = 95th-percentile annual air concentration (pCi/m3

) [cell 

D12] 

2.22 = 2.22 dpm/pCi conversion 

2,400 = 2,400 m3/year inhalation rate

365 = 365 days/yea r 

Branching fraction = alpha branching fraction [column H]

([0 693 - ] ) e . Half life Decay correction time Decay correction factor −÷ × =

And: 

Half-life = half-life [column D] converted to hours 

Decay correction time = air sample decay correction time [cell A12]

5. The table is broken into two sections: potential unmonitored alpha and alpha bioassay 

denoted in column J. 

Unmonitored Alpha Organ Doses 

Note that the doses in these sections are all based on a single year of exposure regardless 

of the actual exposure period since only comparisons are being done and all doses are 

proportional to the intake amount. 

1. The worksheet contains the committed internal dose from the alpha radionuclides with 

half-lives less than 100 days that are assumed not to be detected by the gross alpha 

bioassay method. These doses are presented in Tables 22a and 22b above. The 

radionuclide intake rates and solubility types yielding the highest dose to the organ of 
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

 September 18,2017

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ABRWH (or their technical support and review contractors) positions unless specifically marked as such. This document represents preliminary 

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interest are then run using IMBA or CAD to determine the annual doses for the 1969 

through 1971 monitoring period. 

2. Column C lists the annual intake rates based on BZ data determined in column C of the 

“Alpha Breathing Zone Int Rates” worksheet. 

3. Columns L through O determine the committed organ doses assessed from one year of 

intake for each radionuclide based on the annual BZ intake rates in column C and the 

organ DCFs in columns D though K. 

The Committed Dose to Organ from one year of intake (rem) in columns L through O 

for alpha emitters is determined by the following:

Committed dose = Annual intake rate × DCF × 365 ÷ 1,000 ÷ 2.22

Where:

Committed dose = Committed Dose to Organ from one year of intake (rem) 

[column L through O] 

Annual intake rate = annual intake rate based on BZ data (dpm/day) [column C] 

2.22 = 2.22 dpm/pCi conversion 

1,000 = 1,000 mrem/rem conversion 

365 = 365 days/year 

DCF = ICRP (1995) inhalation maximum organ DCFs (mrem/pCi) [columns D 

through K] 

Gross Alpha Bio Organ Doses 

1. This worksheet determines the intake rate based on gross alpha bioassay and the limiting 

doses based on a comparison of the intake rate based on bioassay to the intake rate based 

on BZ data. These doses are summarized in Tables 21a and 21b above.

2. Column AF contains the alpha branching fractions which are taken from the “Alpha 

Breathing Zone Int Rates” worksheet. 

3. Columns D, F, I, K, N, P, S, and U contain the intake rates and doses based on a urine 

sample result of 1 dpm/sample from the “Doses Based on Bioassay” worksheet.

The Intake Rate (adjusted for MDA and alpha branching fraction) (dpm/day) in 

columns E, J, O, and T are determined by the following: 

Intake rate based on bioassay = Intake rate (1 dpm/sample) × MDA/2 ÷ Branching 

fraction

Where:
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

 September 18,2017

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with the ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or 

ABRWH (or their technical support and review contractors) positions unless specifically marked as such. This document represents preliminary 

positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any 

information that is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.

Intake rate based on bioassay = intake rate (adjusted for MDA and alpha 

branching fraction) (dpm/day) [columns E, J, O, and T]

Intake rate (1 dpm/sample) = intake rate based on urine sample result of 

1 alpha dpm/sample [columns D, I, N, and S] 

MDA = gross alpha bioassay MDA [cell C10]

2 = missed dose divisor 

Branching fraction = alpha branching fraction [column AF] 

4. Columns E, G, J, L, O, Q, T, and V determine the intake rates and missed doses using the 

alpha urine sample result of 1 dpm/sample adjusted for the sample-specific MDA in cell 

C10 and branching fraction in column AF. 

The dose (adjusted for MDA and alpha branching fraction) in columns G. L, Q, and V 

are determined by the following: 

Dose based on bioassay = Dose (1 dpm/sample) × MDA/2 ÷ Branching fraction 

Where:

Dose based on bioassay = dose (adjusted for MDA and alpha branching fraction) 

[columns G. L, Q, and V] 

Dose (1 dpm/sample) = dose based on urine sample result of 1 alpha dpm/sample 

[columns F, K, P, and U] 

MDA = gross alpha bioassay minimum detectable activity [cell C10]

2 = missed dose divisor 

Branching fraction = alpha branching fraction [column AF] 

5. Column W contains the annual intake rates based on BZ data obtained from the “Alpha 

Breathing Zone Int Rates” worksheet. 

6. Columns X through AE determine the more limiting dose based on a comparison of the 

intake rates based on bioassay to the intake rates based on BZ data. If the annual intake 

rate based on BZ data in column W is less than the intake rate adjusted for MDA and 

alpha branching fraction, the dose adjusted for MDA and alpha branching fraction is 

divided by the ratio of intake rate adjusted for MDA and alpha branching fraction to the 

annual intake rate based on BZ data in column W. Otherwise, the dose adjusted for 

MDA and alpha branching fraction is assigned. 

If:

Annual intake rate < Intake rate based on bioassay 

Where:
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

 September 18,2017

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with the ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or 

ABRWH (or their technical support and review contractors) positions unless specifically marked as such. This document represents preliminary 

positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any 

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Intake rate based on bioassay = columns E, J, O, and T 

Annual intake rate = column W

Then: 

Dose = Dose based on bioassay ÷ Ratio of Bioassay Intake to BZ Intake

Where:

Dose based on bioassay = columns G, L, Q, and V 

Ratio of Bioassay Intake to BZ Intake = intake rate based on bioassay ÷ annual 

intake rate

Otherwise:

Dose = Dose based on bioassay 

Unmonitored Worker 67-68 Alpha Doses 

1. The worksheet contains the committed internal doses to an unmonitored worker for 1967 

through 1968 from all the alpha radionuclides. These doses are presented in Tables 26a 

and 26b above. The radionuclide intake rates and solubility types yielding the highest 

dose to the organ of interest are then run using IMBA or CAD to determine the annual 

doses for the unmonitored period 1967 through 1968. 

2. Column C lists the annual intake rates based on BZ data determined in column C of the 

“Alpha Breathing Zone Int Rates” worksheet.

3. Columns L through O determine the committed organ doses assessed from one year of 

intake for each radionuclide based on the annual BZ intake rates in column C and the 

organ DCFs in columns D though K. 

The committed dose to organ from one year of intake (rem) in columns L through O 

for alpha emitters is determined by the following:

Committed dose = Annual intake rate × DCF × 365 ÷ 1,000 ÷ 2.22

Where:

Committed dose = committed dose to organ from one year of intake (rem) 

[column L through O] 

Annual intake rate = annual intake rate based on BZ data (dpm/day) [column C] 

2.22 = 2.22 dpm/pCi conversion 

1,000 = 1,000 mrem/rem conversion 

365 = 365 days/year 
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

 September 18,2017

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with the ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or 

ABRWH (or their technical support and review contractors) positions unless specifically marked as such. This document represents preliminary 

positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any 

information that is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.

DCF = ICRP (1995) inhalation maximum organ DCFs (mrem/pCi) [columns D 

through K] 

BG Breathing Zone Intake Rates

1. This worksheet determines the beta and gamma annual intake rates based on the air 

concentration data from the “Breathing Zone Data” worksheet. The table is broken into 

four sections (denoted in column K): potential unmonitored beta, beta bioassay, potential 

unmonitored gamma, and gamma bioassay radionuclides. The intake rates from Tables 

23b, 24b, 25a, 25b, 27a, and 27b above are used. 

2. Columns D through J contain the decay data taken from Rad ToolBox. Column J is the 

photon yield data, unless noted. 

3. The decay data in columns F through J are referenced in the “Gross Beta Bioassay Organ 

Doses” and “Gross Gamma Bio Organ Doses” worksheets. 

4. Column C determines the annual intake rates using the highest 95th-percentile annual air 

concentration of 4.2 pCi/m3

 for 1967 to 1971 from the “Breathing Zone Data” worksheet, 

decay-corrected back 72 hours and adjusted for beta branching fraction in column H or 

photon yield in column J. 

The annual intake rate based on BZ data (dpm/day or γpm/day) in column C is 

determined by the following methods: 

Beta Emitters:

Annual intake rate = Annual air concentration × 2.22 × 2,400 ÷ 365 ÷ Decay 

correction factor ÷ Branching fraction

Where:

Annual intake rate = annual intake rate based on BZ data (dpm/day or γpm/day) 

[column C] 

Annual air concentration = 95th-percentile annual air concentration (pCi/m3)

[cell D12] 

2.22 = 2.22 dpm/pCi conversion 

2,400 = 2,400 m3/year inhalation rate

365 = 365 days/year 

Branching fraction = beta branching fraction [column H] 

([0 693 - ] ) e . Half life Decay correction time Decay correction factor −÷ × =

And: 
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

 September 18,2017

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with the ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or 

ABRWH (or their technical support and review contractors) positions unless specifically marked as such. This document represents preliminary 

positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any 

information that is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.

Half-life = half-life [column D] converted to hours 

Decay correction time = air sample decay correction time [cell A12]

Gamma Emitters:

Annual intake rate = Annual air concentration × 2.22 × 2,400 ÷ 365 ÷ Decay 

correction factor ÷ Photon yield 

Where:

Annual intake rate = annual intake rate based on BZ data (dpm/day or γpm/day) 

[column C] 

Annual air concentration = 95thpercentile annual air concentration (pCi/m3

)

[cell D12] 

2.22 = 2.22 dpm/pCi conversion 

2,400 = 2,400 m3

/year inhalation rate

365 = 365 days/year 

Photon yield = Photon yield [column J]

([0 693 - ] ) e . Half life Decay correction time Decay correction factor −÷ × =

And: 

Half-life = half-life [column D] converted to hours 

Decay correction time = air sample decay correction time [cell A12]

Unmonitored BG Organ Doses 

1. The worksheet determines the committed internal doses for beta and gamma 

radionuclides with half-lives less than 100 days that are assumed not to be detected by the 

gross beta and gross gamma bioassay methods. These doses are presented in Tables 25a 

and 25b above. The radionuclide intake rates and solubility types yielding the highest 

dose to the organ of interest are then run using IMBA or CAD to determine the annual 

doses for the 1969 through 1971 monitoring period. 

2. Column C lists the annual intake rates based on BZ data determined in column C of the 

“BG Breathing Zone Intake Rates” worksheet. 

3. Columns L through O determine the committed dose for the organs assessed from 

one year of intake for each radionuclide based on the annual BZ intake rates in column C 

and the organ DCFs in columns D though K. 

The Committed Dose to Organ from one year of Intake (rem) in columns L through O 

for beta and gamma emitters is determined by the following:
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

 September 18,2017

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with the ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or 

ABRWH (or their technical support and review contractors) positions unless specifically marked as such. This document represents preliminary 

positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any 

information that is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.

Committed dose = Annual intake rate × DCF x 365 ÷ 1,000 ÷ 2.22

Where:

Committed dose = Committed Dose to Organ from one year of Intake (rem) 

[column L through O] 

Annual intake rate = annual intake rate based on BZ data (dpm/day or γpm/day) 

[column C] 

2.22 = 2.22 dpm/pCi conversion 

1,000 = 1,000 mrem/rem conversion 

365 = 365 days/year 

DCF = ICRP (1995) inhalation maximum organ DCFs (mrem/pCi) [columns D 

through K] 

Gross Beta Bio Organ Doses

1. This worksheet determines the intake rate based on gross beta bioassay and the limiting 

doses based on a comparison of the intake rate based on bioassay to the intake rate based 

on BZ data. These doses are summarized in Tables 23a and 23b above. 

2. Column AF contains the beta branching fractions which are taken from the “BG 

Breathing Zone Intake Rates” worksheet.

3. Columns D, F, I, K, N, P, S, and U contain the intake rates and doses based on a urine 

sample result of 1 dpm/sample from the “Doses Based on Bioassay” worksheet.

4. Columns E, G, J, L, O, Q, T, and V determine the intake rates and missed doses using the 

beta urine sample result of 1 beta dpm/sample adjusted for the sample-specific MDA in 

cell C10 and branching fraction in column AF. 

a. The Intake Rate (adjusted for MDA and beta branching fraction) (dpm/day) in 

columns E, J, O, and T are determined by the following: 

Intake rate based on bioassay = Intake rate (1 dpm/sample) × MDA/2 ÷ 

Branching fraction 

Where:

Intake rate based on bioassay = Intake Rate (adjusted for MDA and beta 

branching fraction) (dpm/day) [columns E, J, O, and T]

Intake rate (1 dpm/sample) = Intake Rate based on urine sample result of 

1 beta dpm/sample [columns D, I, N, and S] 

MDA = gross beta bioassay MDA [cell C10]
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

 September 18,2017

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with the ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or 

ABRWH (or their technical support and review contractors) positions unless specifically marked as such. This document represents preliminary 

positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any 

information that is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.

2 = missed dose divisor 

Branching fraction = beta branching fraction [column AF] 

b. The dose (adjusted for MDA and beta branching fraction) in columns G, L, Q, and V 

is determined by the following:

Dose based on bioassay = Dose (1 dpm/sample) × MDA/2 ÷ Branching fraction 

Where:

Dose based on bioassay = Dose (adjusted for MDA and beta branching 

fraction) [columns G, L, Q, and V] 

Dose (1 dpm/sample) = Dose based on urine sample result of 

1 beta dpm/sample [columns F, K, P, and U] 

MDA = gross beta bioassay MDA [cell C10]

2 = missed dose divisor 

Branching fraction = beta branching fraction [column AF] 

5. Column W contains the annual intake rates based on BZ data obtained from column C the 

“BG Breathing Zone Intake Rates” worksheet. 

6. Columns X through AE determine the more limiting dose based on a comparison of the 

intake rates based on bioassay to the intake rates based on BZ data. If the annual intake 

rate based on BZ data in column W is less than the intake rate adjusted for MDA and beta 

branching fraction, the dose adjusted for MDA and beta branching fraction is divided by 

the ratio of intake rate adjusted for MDA and beta branching fraction to the annual intake 

rate based on BZ data in column W. Otherwise, the dose adjusted for MDA and beta 

branching fraction is assigned. 

If:

Annual intake rate < Intake rate based on bioassay 

Where:

Intake rate based on bioassay = columns E, J, O, and T 

Annual intake rate = column W

Then: 

Dose = Dose based on bioassay ÷ Ratio of Bioassay Intake to BZ Intake 

Where:

Dose based on bioassay = columns G, L, Q, and V 
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

 September 18,2017

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with the ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or 

ABRWH (or their technical support and review contractors) positions unless specifically marked as such. This document represents preliminary 

positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any 

information that is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.

Ratio of Bioassay Intake to BZ Intake = Intake rate based on bioassay ÷ Annual 

intake rate 

Otherwise:

Dose = Dose based on bioassay 

Gross Gamma Bio Organ Doses

1. This worksheet determines the intake rate based on gross gamma bioassay and the 

limiting doses based on a comparison of the intake rate based on bioassay to the intake 

rate based on BZ data. These doses are summarized in Tables 24a and 24b above. 

2. Column AF contains the photon yield which are taken from the “BG Breathing Zone 

Intake Rates” worksheet. 

3. Columns D, F, I, K, N, P, S, and U contain the intake rates and doses based on a urine 

sample result of 1 dpm/sample from the “Doses Based on Bioassay” worksheet.

4. Columns E, G, J, L, O, Q, T, and V determines the intake rates and missed doses using 

the gamma urine sample result of 1 γpm/sample adjusted for the sample-specific MDA in 

cell C10, and photon yield in column AJ. 

a. The Intake Rate (adjusted for MDA and γ yield) (dpm/day) in columns E, J, O, and T 

are determined by the following: 

Intake rate based on bioassay = Intake rate (1 γpm/sample) × MDA/2 ÷ Photon 

yield

Where:

Intake rate based on bioassay = Intake Rate (adjusted for MDA and γ yield) 

(dpm/day) [columns E, J, O, and T]

Intake rate (1 dpm/sample) = Intake Rate based on urine sample result of 1 

γpm/sample [columns D, I, N, and S] 

MDA = gross gamma bioassay MDA [cell C10]

2 = missed dose divisor 

Photon yield = Photon yield [column AF] 

b. The Dose (adjusted for MDA and γ yield) in columns G. L, Q, and V are determined 

by the following:

Dose based on bioassay = Dose (1 dpm/sample) × MDA/2 ÷ Photon yield 

Where:
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

 September 18,2017

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with the ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or 

ABRWH (or their technical support and review contractors) positions unless specifically marked as such. This document represents preliminary 

positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any 

information that is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.

Dose based on bioassay = Dose (adjusted for MDA and γ yield) [columns G, 

L, Q, and V] 

Dose (1 dpm/sample) = Dose based on gamma urine sample result of 

1 γpm/sample [columns F, K, P, and U] 

MDA = gross gamma bioassay MDA [cell C10]

2 = missed dose divisor 

Photon yield = Photon yield [column AF] 

5. Column W contains the annual intake rates based on BZ data obtained from column C of 

the “BG Breathing Zone Intake Rates” worksheet. 

6. Columns X through AE determines the more limiting dose based on a comparison of the 

intake rates based on bioassay to the intake rates based on BZ data. If the annual intake 

rate based on BZ data in column W is less than the intake rate adjusted for MDA and 

photon yield, the dose adjusted for MDA and photon yield is divided by the ratio of 

intake rate adjusted for MDA and photon yield to the annual intake rate based on BZ data 

in column W. Otherwise, the dose adjusted for MDA and photon yield is assigned. 

If:

Annual intake rate < Intake rate based on bioassay 

Where:

Intake rate based on bioassay = columns E, J, O, and T 

Annual intake rate = column W

Then: 

Dose = Dose based on bioassay ÷ Ratio of Bioassay Intake to BZ Intake 

Where:

Dose based on bioassay = columns G, L, Q, and V 

Ratio of Bioassay Intake to BZ Intake = Intake rate based on bioassay ÷ 

Annual intake rate

Otherwise:

Dose = Dose based on bioassay 

Unmonitored Worker BG Doses 67-68 

1. The worksheet contains the committed internal doses to an unmonitored worker for 1967 

through 1968 from beta and gamma radionuclides. These doses are presented in Table 
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

 September 18,2017

Page 74 of 103

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with the ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or 

ABRWH (or their technical support and review contractors) positions unless specifically marked as such. This document represents preliminary 

positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any 

information that is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.

27a and 27b above. The radionuclide intake rates and solubility types yielding the 

highest dose to the organ of interest are then run using IMBA or CAD to determine the 

annual doses for the unmonitored period 1967 through 1968. 

2. Column C lists the annual intake rates based on BZ data determined in column C of the 

“BG Breathing Zone Intake Rates” worksheet. 

3. Columns L through O determine the committed dose for the organs assessed from 

one year of intake for each radionuclide based on the annual BZ intake rates in column C 

and the organ DCFs in columns D though K. 

The Committed Dose to Organ from one year of Intake (rem) in columns L through O 

for beta and gamma emitters is determined by the following:

Committed dose = Annual intake rate × DCF × 365 ÷ 1,000 ÷ 2.22

Where:

Committed dose = Committed Dose to Organ from one year of Intake (rem) 

[column L through O] 

Annual intake rate = annual intake rate based on BZ data (dpm/day or γpm/day) 

[column C] 

2.22 = 2.22 dpm/pCi conversion 

1,000 = 1,000 mrem/rem conversion 

365 = 365 days/year 

DCF = ICRP (1995) inhalation maximum organ DCFs (mrem/pCi) [columns D 

through K] 

Example Calculations 

The following provides example calculations for the methods described above in the worksheets: 

Alpha Breathing Zone Int Rates

Example for Ac-225 

The annual intake rate based on BZ data (dpm/day) in cell C14 is 0.60 dpm/day. 

Annual intake rate = Annual air concentration × 2.22 × 2,400 ÷ 365 ÷ Decay correction factor ÷ 

Branching fraction

Annual air concentration = 0.0336 pCi/m3 [cell D12] 

2.22 = 2.22 dpm/pCi conversion 

2,400 = 2,400 m3

/year inhalation rate
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

 September 18,2017

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365 = 365 days/year 

Branching fraction = 1 [cell H14] 

Half-Life = 10 days [cells D10 and E10] 

Decay correction time = 72 hours [cell A12]

([0 693 10 days 24 hours/day 72 hours ] ) e 0 812 . Decay correction factor . −÷× × = =

Annual intake rate = 0.0336 pCi/m3 × 2.22 dpm/pCi × 2,400 m3/year ÷ 365 days/year ÷ 0.812 ÷ 1

Annual intake rate = 0.60 dpm/day 

Annual intake rate based on BZ data in cell C14 = 0.60 dpm/day. 

Unmonitored Alpha Organ Doses 

Example for Ac-225 

1. The Annual intake rate based on BZ data (dpm/day) in cell C14 is 0.60 dpm/day and is 

taken from the “Alpha Breathing Zone Int Rates” worksheet validated above. 

2. The Committed Dose to Organ from one year of Intake (rem) in cells L14 through O14 

are:

Lung = 1.986E-02 rem [cell L14] 

Bone surface = 1.030E-02 rem [cell M14] 

Liver = 2.758E-03 rem [cell N14]

Adrenals = 4.045E-06 rem [cell O14]

Committed dose = Annual intake rate × DCF x 365 ÷ 1,000 ÷ 2.22

DCF = 2.000E-01 mrem/pCi [cell D14] (lung) 

DCF = 1.037E-01 mrem/pCi [cell F14] (bone surface) 

DCF = 2.778E-02 mrem/pCi [cell H14] (liver)

DCF = 4.074E-05 mrem/pCi [cell J14] (adrenals)

Committed dose (lung) = 0.60 dpm/day × 2.000E-01 mrem/pCi × 365 days/year ÷ 

1,000 mrem/rem ÷ 2.22 dpm/pCi 

Committed dose (lung) = 1.986E-02 rem 

Committed dose (bone surface) = 0.60 dpm/day × 1.037E-01 mrem/pCi × 

365 days/year ÷ 1,000 mrem/rem ÷ 2.22 dpm/pCi 

Committed dose (bone surface) = 1.030E-02 rem 
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

 September 18,2017

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Committed dose (liver) = 0.60 dpm/day × 2.778E-02 mrem/pCi × 365 days/year ÷ 

1,000 mrem/rem ÷ 2.22 dpm/pCi 

Committed dose (liver) = 2.758E-03 rem

Committed dose (adrenals) = 0.60 dpm/day × 4.074E-05 mrem/pCi × 365 days/year ÷ 

1,000 mrem/rem ÷ 2.22 dpm/pCi 

Committed dose (adrenals) = 4.045E-06 rem 

Gross Alpha Bio Organ Doses 

Example for Am-241 

The intake rates based on a urine sample result of 1 dpm/sample in cells D13, I13, N13, and S13 

are taken from row 77 of the “Doses Based on Bioassay” worksheet. 

Intake rate (1 dpm/sample) 

Lung = 93.99 dpm/day [cell D13] 

Bone surface = 93.99 dpm/day [cell I13] 

Liver = 93.99 dpm/day [cell N13] 

Adrenals = 93.99 dpm/day [cell S13] 

The doses based on a urine sample result of 1 dpm/sample in F13, K13, P13, and U13 are taken 

from row 77 of the “Doses Based on Bioassay” worksheet. 

Dose (1 dpm/sample) 

Lung = 3.78E+00 rem [cell F13] 

Bone surface = 2.65E+01 rem [cell K13]

Liver = 4.93E+00 rem [cell P13] 

Adrenals = 2.27E-02 rem [cell U13] 

1. Intake Rates based on bioassay [columns E, J, O, and T]: 

Intake rate based on bioassay = Intake rate (1 dpm/sample) × MDA/2 ÷ Branching 

fraction

MDA = 0.2 dpm/sample [cell C10] 

Branching fraction = 1 [cell AF13] 

Intake rate based on bioassay (lung) = 93.99 dpm/day × 0.2 dpm/sample ÷ 2 ÷ 1 

Intake rate based on bioassay (lung) = 9.40 dpm/day [cell E13] 
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

 September 18,2017

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Intake rate based on bioassay (bone surface) = 93.99 dpm/day × 0.2 dpm/sample ÷ 2 ÷ 1 

Intake rate based on bioassay (bone surface) = 9.40 dpm/day [cell J13] 

Intake rate based on bioassay (liver) = 93.99 dpm/day × 0.2 dpm/sample ÷ 2 ÷ 1 

Intake rate based on bioassay (liver) = 9.40 dpm/day [cell O13] 

Intake rate based on bioassay (adrenals) = 93.99 dpm/day × 0.2 dpm/sample ÷ 2 ÷ 1 

Intake rate based on bioassay (adrenals) = 9.40 dpm/day [cell T13] 

2. Doses based on bioassay [columns G. L, Q, and V]:

The Dose (adjusted for MDA and alpha branching fraction) are:

Lung = 3.78E-01 rem [cell G13] 

Bone surface = 2.65E+00 rem [cell L13] 

Liver = 4.93E-01 rem [cell Q13] 

Adrenals = 2.27E-03 rem [cell V13] 

Dose based on bioassay = Dose (1 dpm/sample) × MDA/2 ÷ Branching fraction

MDA = 0.2 dpm/sample [cell C10] 

Branching fraction = 1 [cell AF13] 

Dose based on bioassay (lung) = 3.78E+00 rem × 0.2 dpm/sample ÷ 2 ÷ 1 

Dose based on bioassay (lung) = 3.78E-01 rem [cell G13] 

Dose based on bioassay (bone surface) = 2.65E+01 rem × 0.2 dpm/sample ÷ 2 ÷ 1 

Dose based on bioassay (bone surface) = 2.65E+00 rem [cell L13]

Dose based on bioassay (liver) = 4.93E+00 rem × 0.2 dpm/sample ÷ 2 ÷ 1 

Dose based on bioassay (liver) = 4.93E-01 rem [cell Q13] 

Dose based on bioassay (adrenals) = 2.27E-02 rem × 0.2 dpm/sample ÷ 2 ÷ 1 

Dose based on bioassay (adrenals) = 2.27E-03 rem [cell V13] 

3. Annual intake rates based on BZ data [column W]:

The annual intake rate based on BZ data in cell W13 is 0.49 dpm/day and is taken 

from cell C20 of the “Alpha Breathing Zone Int Rates” worksheet. The “Alpha 

Breathing Zone Int Rates” spreadsheet results were previously validated above.

4. Limiting dose based on a comparison of intake rates based on bioassay to intake rates

based on BZ Data [columns X, Z, AB, AD]:
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

 September 18,2017

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The limiting doses based on a comparison of intake rates based on bioassay to intake 

rates based on BZ data in cells X13, Z13, AB13, and AD13 are:

Lung = 1.97E-02 rem [cell X13] 

Bone surface = 1.38E-01 rem [cell Z13] 

Liver = 2.57E-02 rem [cell AB13] 

Adrenals = 1.18E-04 rem [cell AD13] 

The Annual intake rate above is 0.49 dpm/day [cell W13].

The Intake rate based on bioassay for all organs assessed = 9.40 dpm/day [cells E13, 

J13, O13, and T13] 

Therefore:

Annual intake rate < Intake rate based on bioassay 

Ratio of Bioassay Intake to BZ Intake = 9.40 dpm/day ÷ 0.49 dpm/day 

Ratio of Bioassay Intake to BZ Intake = 19.16 

Dose = Dose based on bioassay ÷ Ratio of Bioassay Intake to BZ Intake

Dose (lung) = 3.78E-01 rem ÷ 19.16 

Dose (lung) = 1.97E-02 rem [cell X13] 

Dose (bone surface) = 2.65E+00 rem ÷ 19.16 

Dose (bone surface) = 1.38E-01 rem [cell Z13] 

Dose (liver) = 4.93E-01 rem ÷ 19.16 

Dose (liver) = 2.57E-02 rem [cell AB13] 

Dose (adrenals) = 2.27E-03 rem ÷ 19.16 

Dose (adrenals) = 1.18E-04 rem [cell AD13] 
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

 September 18,2017

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BG Breathing Zone Intake Rates

Beta Example for Cu-64

The annual intake rate based on BZ data (dpm/day) in cell C14 is 7.991E+03 dpm/day. 

Annual intake rate = Annual air concentration × 2.22 × 2,400 ÷ 365 ÷ Decay correction factor ÷ 

Branching fraction

Annual air concentration = 4.2 pCi/m3 [cell D12] 

2.22 = 2.22 dpm/pCi conversion 

2,400 = 2,400 m3/year inhalation rate

365 = 365 days/year 

Branching fraction = 0.39 [cell H14] 

Half-Life = 12.701 hours [cells D10 and E10] 

Decay correction time = 72 hours [cell A12]

([0 693 12 701 hours 72 hours ] ) e 0 01967 . . Decay correction factor . −÷ × = =

Annual intake rate = 4.2 pCi/m3 × 2.22 dpm/pCi × 2,400 m3/year ÷ 365 days/year ÷ 0.01967 ÷ 

0.39 

Annual intake rate = 7.991E+03 dpm/day 

Annual intake rate based on BZ data (dpm/day) in cell C14 = 7.991E+03 dpm/day. 

Gamma Example for Y-86 

The annual intake rate based on BZ data (dpm/day) in cell C87 is 5.665E+02 dpm/day. 

Annual intake rate = Annual air concentration × 2.22 × 2,400 ÷ 365 ÷ Decay correction factor ÷ 

Gamma yield

Annual air concentration = 4.2 pCi/m3 [cell D12] 

2.22 = 2.22 dpm/pCi conversion 

2,400 = 2,400 m3/year inhalation rate

365 = 365 days/year 

Gamma Yield = 3.20 [cell J87] 

Half-Life = 14.74 hours [cells D87 and E87] 

Decay correction time = 72 hours [cell A12]

([0 693 14 74 hours 72 hours ] ) e 0 0339 . . Decay correction factor . −÷ × = =
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

 September 18,2017

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Annual intake rate = 4.2 pCi/m3 × 2.22 dpm/pCi × 2,400 m3/year ÷ 365 days/year ÷ 0.0339 ÷ 

3.20 

Annual intake rate = 5.665E+02 dpm/day 

Annual intake rate based on BZ data (dpm/day) in cell C87 = 5.665E+02 dpm/day. 

Unmonitored BG Organ Doses 

Beta Example for Cu-64

1. The annual intake rate based on BZ data (dpm/day) in cell C14 is 7.991E+03 dpm/day

and is taken from the “BG Breathing Zone Intake Rates” worksheet validated above.

2. The Committed Dose to Organ from one year of Intake (rem) in cells L14 trough O14

are:

Lung = 2.676E-03 rem [cell L14] 

Bone surface = 6.326E-05 rem [cell M14] 

Liver = 1.362E-04 rem [cell N14]

Adrenals = 5.839E-05 rem [cell O14]

Committed dose = Annual intake rate × DCF × 365 ÷ 1,000 ÷ 2.22

DCF = 2.037E-06 mrem/pCi [cell D14] (lung) 

DCF = 4.815E-08 mrem/pCi [cell F14] (bone surface) 

DCF = 1.037E-07 mrem/pCi [cell H14] (liver)

DCF = 4.444E-08 mrem/pCi [cell J14] (adrenals)

Committed dose (lung) = 7.991E+03 dpm/day × 2.037E-06 mrem/pCi × 

365 days/year ÷ 1,000 mrem/rem ÷ 2.22 dpm/pCi 

Committed dose (lung) = 2.676E-03 rem 

Committed dose (bone surface) = 7.991E+03 dpm/day x 4.815E-08 mrem/pCi × 

365 days/year ÷ 1,000 mrem/rem ÷ 2.22 dpm/pCi 

Committed dose (bone surface) = 6.326E-05 rem 

Committed dose (liver) = 7.991E+03 dpm/day × 1.037E-07 mrem/pCi × 

365 days/year ÷ 1,000 mrem/rem ÷ 2.22 dpm/pCi 

Committed dose (liver) = 1.362E-04 rem 
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

 September 18,2017

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Committed dose (adrenals) = 7.991E+03 dpm/day × 4.444E-08 mrem/pCi × 

365 days/year ÷ 1,000 mrem/rem ÷ 2.22 dpm/pCi 

Committed dose (adrenals) = 5.839E-05 rem 

Gamma Example for Y-86 

1. The annual intake rate based on BZ data (dpm/day) in cell C59 is 5.665E+02 dpm/day

and is taken from the “BG Breathing Zone Intake Rates” worksheet validated above.

2. The Committed Dose to Organ from one year of Intake (rem) in cells L59 through O59

are:

Lung = 2.104E-04 rem [cell L59] 

Bone surface = 3.449E-05 rem [cell M59]

Liver = 3.794E-05 rem [cell N59]

Adrenals = 2.863E-05 rem [cell O59]

Committed dose = Annual intake rate × DCF × 365 ÷ 1,000 ÷ 2.22

DCF = 2.259E-06 mrem/pCi [cell D59] (lung) 

DCF = 3.704E-07 mrem/pCi [cell F59] (bone surface) 

DCF = 4.074E-07 mrem/pCi [cell H59] (liver)

DCF = 3.074E-07 mrem/pCi [cell J59] (adrenals)

Committed dose (lung) = 5.665E+02 dpm/day × 2.259E-06 mrem/pCi × 

365 days/year ÷ 1,000 mrem/rem ÷ 2.22 dpm/pCi 

Committed dose (lung) = 2.104E-04 rem 

Committed dose (bone surface) = 5.665E+02 dpm/day × 3.704E-07 mrem/pCi × 

365 days/year ÷ 1,000 mrem/rem ÷ 2.22 dpm/pCi 

Committed dose (bone surface) = 3.449E-05 rem 

Committed dose (liver) = 5.665E+02 dpm/day × 4.074E-07 mrem/pCi × 

365 days/year ÷ 1,000 mrem/rem ÷ 2.22 dpm/pCi

Committed dose (liver) = 3.794E-05 rem 

Committed dose (adrenals) = 5.665E+02 dpm/day × 3.074E-07 mrem/pCi × 

365 days/year ÷ 1,000 mrem/rem ÷ 2.22 dpm/pCi 

Committed dose (adrenals) = 2.863E-05 rem 
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

 September 18,2017

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Gross Beta Bioassay Organ Doses

Beta Example for Ag-110m 

1. The intakes rates based on a urine sample result of 1 dpm/sample in cells D13, I13, N13,

and S13 are taken from row 18 of the “Doses Based on Bioassay” worksheet.

Intake rate (1 dpm/sample) 

Lung = 1109.00 dpm/day [cell D13] 

Bone surface = 1109.00 dpm/day [cell I13] 

Liver = 1109.00 dpm/day [cell N13] 

Adrenals = 1109.00 dpm/day [cell S13] 

The doses based on a urine sample result of 1 dpm/sample in F13, K13, P13, and U13 

are taken from row 18 of the “Doses Based on Bioassay” worksheet. 

Dose (1 dpm/sample) 

Lung = 7.75E-02 rem [cell F13] 

Bone surface = 4.25E-03 rem [cell K13] 

Liver = 1.42E-02 rem [cell P13] 

Adrenals = 9.96E-03 rem [cell U13] 

2. Intake Rates based on bioassay [columns E, J, O, and T]:

Intake rate based on bioassay = Intake rate (1 dpm/sample) × MDA/2 ÷ Branching 

fraction

MDA = 2 dpm/sample [cell C10] 

Branching fraction = 0.9864 [cell AF13] 

Intake rate based on bioassay (lung) = 1109.00 dpm/day × 2 dpm/sample ÷ 2 ÷ 

0.9864 

Intake rate based on bioassay (lung) = 1124.29 dpm/day [cell E13] 

Intake rate based on bioassay (bone surface) = 1109.00 dpm/day × 2 dpm/sample ÷ 

2 ÷ 0.9864 

Intake rate based on bioassay (bone surface) = 1124.29 dpm/day [cell J13] 

Intake rate based on bioassay (liver) = 1109.00 dpm/day × 2 dpm/sample ÷ 2 ÷ 

0.9864 

Intake rate based on bioassay (liver) = 1124.29 dpm/day [cell O13] 
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

 September 18,2017

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Intake rate based on bioassay (adrenals) = 1109.00 dpm/day × 2 dpm/sample ÷ 2 ÷ 

0.9864 

Intake rate based on bioassay (adrenals) = 1124.29 dpm/day [cell T13] 

3. Doses based on bioassay [columns G. L, Q, and V]:

The Dose (adjusted for MDA and alpha branching fraction) are: 

Lung = 7.86E-02 rem [cell G13] 

Bone surface = 4.31E-03 rem [cell L13] 

Liver = 1.44E-02 rem [cell Q13] 

Adrenals = 1.01E-02 rem [cell V13] 

Dose based on bioassay = Dose (1 dpm/sample) × MDA/2 ÷ Branching fraction

MDA = 2 dpm/sample [cell C10] 

Branching fraction = 0.9864 [cell AF13] 

Dose based on bioassay (lung) = 7.75E-02 rem × 2 dpm/sample ÷ 2 ÷ 0.9864 

Dose based on bioassay (lung) = 7.86E-02 rem [cell G13] 

Dose based on bioassay (bone surface) = 4.25E-03 rem × 2 dpm/sample ÷ 2 ÷ 0.9864 

Dose based on bioassay (bone surface) = 4.31E-03 rem [cell L13]

Dose based on bioassay (liver) = 1.42E-02 rem × 2 dpm/sample ÷ 2 ÷ 0.9864 

Dose based on bioassay (liver) = 1.44E-02 rem [cell Q13] 

Dose based on bioassay (adrenals) = 9.96E-03 rem × 2 dpm/sample ÷ 2 ÷ 0.9864 

Dose based on bioassay (adrenals) = 1.01E-02 rem [cell V13] 

4. Annual intake rates based on BZ data [column W]:

The annual intake rate based on BZ data in cell W13 is 62.67 dpm/day and is taken 

from cell C62 of the “BG Breathing Zone Intake Rates” worksheet. The “BG 

Breathing Zone Intake Rates” spreadsheet results were previously validated above. 

5. Limiting dose based on a comparison of intake rates based on bioassay to intake rates

based on BZ data [columns X, Z, AB, and AD]:

The limiting doses based on a comparison of intake rates based on bioassay to intake 

rates based on BZ data in cells X13, Z13, Z13, and AD13 are:

Lung = 4.38E-03 rem [cell X13] 

Bone surface = 2.40E-04 rem [cell Z13] 
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

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 September 18,2017

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Liver = 8.03E-04 rem [cell AB13] 

Adrenals = 5.63E-04 rem [cell AD13] 

The Annual intake rate above is 62.67 dpm/day [cell W13]. 

The Intake rate based on bioassay for all organs assessed = 1,124.29 dpm/day 

[cells E13, J13, O13, and T13] 

Therefore:

Annual intake rate < Intake rate based on bioassay 

Ratio of Bioassay Intake to BZ Intake = 1,124.29 dpm/day ÷ 62.67 dpm/day 

Ratio of Bioassay Intake to BZ Intake = 17.94 

Dose = Dose based on bioassay ÷ Ratio of Bioassay Intake to BZ Intake 

Dose (lung) = 7.86E-02 rem ÷ 17.94 

Dose (lung) = 4.38E-03 rem [cell X13] 

Dose (bone surface) = 4.31E-03 rem ÷ 17.94 

Dose (bone surface) = 2.40E-04 rem [cell Z13] 

Dose (liver) = 1.44E-02 rem ÷ 17.94 

Dose (liver) = 8.03E-04 rem [cell AB13] 

Dose (adrenals) = 1.01E-02 rem ÷ 17.94 

Dose (adrenals) = 5.63E-04 rem [cell AD13] 

Gross Gamma Bio Organ Doses

Gamma Example for Ag-108m 

1. The intakes rates based on a urine sample result of 1 dpm/sample in cells D13, I13, N13,

and S13 are taken from row 17 of the “Doses Based on Bioassay” worksheet.

Intake rate (1 dpm/sample) 

Lung = 828.64 dpm/day [cell D13] 

Bone surface = 828.64 dpm/day [cell I13] 

Liver = 828.64 dpm/day [cell N13] 

Adrenals = 828.64 dpm/day [cell S13] 

The doses based on a urine sample result of 1 dpm/sample in F13, K13, P13, and U13 

are taken from row 17 of the “Doses Based on Bioassay” worksheet. 
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

 September 18,2017

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Dose (1 dpm/sample) 

Lung = 1.06E-01 rem [cell F13] 

Bone surface = 5.79E-03 rem [cell K13] 

Liver = 1.71E-02 rem [cell P13] 

Adrenals = 1.38E-02 rem [cell U13] 

2. Intake rates based on bioassay [columns E, J, O, and T]:

Intake rate based on bioassay = Intake rate (1 dpm/sample) × MDA/2 ÷ Photon yield 

MDA = 100 dpm/sample [cell C10] 

Photon yield = 2.79 [cell AF13] 

Intake rate based on bioassay (lung) = 828.64 dpm/day × 100 dpm/sample ÷ 2 ÷ 2.79 

Intake rate based on bioassay (lung) = 14,860.83 dpm/day [cell E13] 

Intake rate based on bioassay (bone surface) = 828.64 dpm/day × 100 dpm/sample ÷ 

2 ÷ 2.79 

Intake rate based on bioassay (bone surface) = 14,860.83 dpm/day [cell J13]

Intake rate based on bioassay (liver) = 828.64 dpm/day × 100 dpm/sample ÷ 2 ÷ 2.79 

Intake rate based on bioassay (liver) = 14,860.83 dpm/day [cell O13] 

Intake rate based on bioassay (adrenals) = 828.64 dpm/day × 100 dpm/sample ÷ 2 ÷ 

2.79 

Intake rate based on bioassay (adrenals) = 14,860.83 dpm/day [cell T13] 

3. Doses based on bioassay [columns G. L, Q, and V]:

The Dose (adjusted for MDA and alpha branching fraction) are: 

Lung = 1.89E+00 rem [cell G13] 

Bone surface = 1.04E-01 rem [cell L13] 

Liver = 3.07E-01 rem [cell Q13] 

Adrenals = 2.48E-01 rem [cell V13] 

Dose based on bioassay = Dose (1 dpm/sample) × MDA/2 ÷ Photon yield

MDA = 100 dpm/sample [cell C10] 

Photon yield = 2.79 [cell AF13] 

Dose based on bioassay (lung) = 1.06E-01 rem × 100 dpm/sample ÷ 2 ÷ 2.79 

Dose based on bioassay (lung) = 1.89E+00 rem [cell G13] 
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

 September 18,2017

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Dose based on bioassay (bone surface) = 5.79E-03 rem × 100 dpm/sample ÷ 2 ÷ 2.79 

Dose based on bioassay (bone surface) = 1.04E-01 rem [cell L13]

Dose based on bioassay (liver) = 1.71E-02 rem × 100 dpm/sample ÷ 2 ÷ 2.79 

Dose based on bioassay (liver) = 3.07E-01 rem [cell Q13] 

Dose based on bioassay (adrenals) = 1.38E-02 rem × 100 dpm/sample ÷ 2 ÷ 2.79 

Dose based on bioassay (adrenals) = 2.48E-01 rem [cell V13] 

4. Annual intake rates based on BZ data [column W]:

The annual intake rate based on BZ data in cell W13 is 21.99 dpm/day and is taken 

from cell C155 of the “BG Breathing Zone Intake Rates” worksheet. The “BG 

Breathing Zone Intake Rates” spreadsheet results were previously validated above. 

5. Limiting dose based on a comparison of intake rates based on bioassay to intake rates

based on BZ Data [columns X, Z, AB, and AD]:

The limiting doses based on a comparison of intake rates based on bioassay to intake 

rates based on BZ data in cells X13, Z13, AB13, and AD13 are:

Lung = 2.80E-03 rem [cell X13] 

Bone surface = 1.54E-04 rem [cell Z13] 

Liver = 4.55E-04 rem [cell AB13] 

Adrenals = 3.67E-04 rem [cell AD13] 

The Annual intake rate above is 21.99 dpm/day [cell W13]. 

The Intake rate based on bioassay for all organs assessed = 14860.83 dpm/day [cells 

E13, J13, O13, and T13] 

Therefore:

Annual intake rate < Intake rate based on bioassay 

Ratio of Bioassay Intake to BZ Intake = 14,860.83 dpm/day ÷ 21.99 dpm/day 

Ratio of Bioassay Intake to BZ Intake = 675.77 

Dose = Dose based on bioassay ÷ Ratio of Bioassay Intake to BZ Intake

Dose (lung) = 1.89E+00 rem ÷ 675.77 

Dose (lung) = 2.80E-03 rem [cell X13] 

Dose (bone surface) = 1.04E-01 rem ÷ 675.77 

Dose (bone surface) = 1.54E-04 rem [cell Z13] 

Dose (liver) = 3.07E-01 rem ÷ 675.77 

Dose (liver) = 4.55E-04 rem [cell AB13] 
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

 September 18,2017

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Dose (adrenals) = 2.48E-01 rem ÷ 675.77 

Dose (adrenals) = 3.67E-04 rem [cell AD13] 
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

 September 18,2017

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ATTACHMENT B

LBNL Air Concentration Data Exposure Model Description

The data used for the statistical reduction of the LBNL air sample data was obtained from the 

LBNL Dual Data Entry Phase I and II BZ data effort. There were two sets of data entered for the 

LBNL Dual Data Entry Phase I and II efforts. These two databases were comprised from a 

number of LBNL air sample reports (LBNL 1963, 1993; LRL-B 1962a, 1962b, 1962c, 1963a, 

1963b, 1984). 

LBNL monthly summary air sample reports that listed BZ locations that were greater than or 

equal to 1% of the MPC for the unknown alpha and beta/gamma emitters were entered for the 

LBNL Dual Data Entry Phase I effort. This available air sample data was from September 1963 

through 1987. There was air sample data from 1962 to mid-1963 in this data set that was not 

monthly average air concentrations data. There were computer printouts of monthly average air 

concentrations for each air sampling location for 1962 and 1963 that were used to determine the 

annual average air concentrations for these years. This 1962 and 1963 air sample data were in 

units of pCi/m3

, and were entered as part of the LBNL Dual Data Entry Phase II effort. 

There were also some gaps in the above data. These were missing monthly air sample summary 

reports in the mid to late 1980’s. Computer printouts of LBNL air concentration data for LBNL 

were used to fill in these gaps. This available data was from December 1984, and January 1993 

to June 1993. The December 1984 data were monthly average air concentrations for each air 

sampling location. The January 1993 to June 1993 data was six months of data for each 

sampling location. These data were in units of pCi/m3

, and were entered for the LBNL Dual 

Data Entry Phase II effort.

It should be noted that this exposure model for the LBNL air sample data assumed censored 

values for non-reported zero or negative air sample data, as explained in the data discussions 

below. 

It should also be noted that a majority of the air sample data was censored for 1964 through 1987 

since these data were based on monthly summary air sample reports that listed BZ locations that 

were greater than or equal to 1% of the MPC. Tables B-1 and B-2 provide the uncensored 

months, the total number of months, and number of locations for the alpha and beta models 

sampled. These uncensored months were the air samples results obtained from the monthly air 

sample summary reports entered in the LBNL Dual Data Entry Phase I effort.

Tables B-5 and B-6 following this section provide details of the available BZ data used from the 

LBNL Dual Data Entry Phase I and II efforts. 

The methods for determining the annual average air concentrations are described below. 
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Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

 September 18,2017

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information that is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.

1962 

For January 1962 through December 1962, there was monthly air sample computer printout data. 

The annual average air concentrations were determined by the following: 

1. “ENV,” which were environmental Filter Queen locations, were excluded from the data.

The “2 STRM” location was excluded as this was not a building room sample location.

2. Blank alpha and beta/gamma monthly average air concentrations were assigned an

average alpha and average beta/gamma air concentration values of 0.001 pCi/m3 and

0.01 pCi/m3, respectively. This corresponded to the lowest alpha and beta/gamma

monthly average air concentrations reported for any sample location in the data set.

Table B-1. Uncensored Alpha Months, Total Months, and Number of 

Air Sampling Locations. 

Year

Uncensored Alpha 

Months Total Months

Number of Air 

Sampling Locations

1964 26 1,620 135

1965 24 1,608 134

1966 17 1,740 145

1967 22 1,968 164

1968 22 2,028 169

1969 16 1,908 159

1970 20 1,752 146

1971 24 1,560 130

1972 35 1,452 121

1973 20 1,536 128

1974 28 1,416 118

1975 20 1,284 107

1976 8 1,224 102

1977 16 1,176 98

1978 7 1,056 88

1979 6 1,044 87

1980 7 1,092 91

1981 8 1,128 94

1982 14 1,056 88

1983 5 1,020 85

1984 27 972 81

1985 5 948 79

1986 2 948 79

1987 19 948 79

Refer to items 1 and 2 of the September 1963 through 1987 section below for the percent 

maximum permissible concentration (MPC)/derived concentration guide (DCG) 

conversions for this period. 
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

 September 18,2017

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ABRWH (or their technical support and review contractors) positions unless specifically marked as such. This document represents preliminary 

positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any 

information that is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.

3. All unreported air concentrations (i.e., a given month/location combination is not

reported) were assigned an average alpha and average beta/gamma air concentration

values of 0.001 pCi/m3and 0.01 pCi/m3, respectively.

4. Any location that was reported at least once in 1962 was assumed to have 12 monthly

means for the alpha air concentration and 12 monthly means for the beta/gamma air

concentration.

5. The alpha annual average air concentration for each BZ location was determined by

averaging the alpha air concentrations for the year. This is the maximum possible mean

(MPM) for each location.

6. The beta/gamma annual average air concentration for each BZ location was determined

by averaging the beta/gamma air concentrations for the year. This is the MPM for each

location.

7. The empirical 95th percentile of the annual alpha MPM for all locations for 1962 was

determined.
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

 September 18,2017

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information that is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.

Table B-2. Uncensored Beta/Gamma Months, Total Months, and Number of 

Air Sampling Locations. 

Year

Uncensored 

Beta/Gamma 

Months Total Months

Number of Air 

Sampling Locations

1964 26 1,620 135

1965 24 1,608 134

1966 17 1,740 145

1967 22 1,968 164

1968 22 2,028 169

1969 16 1,908 159

1970 20 1,752 146

1971 24 1,560 130

1972 35 1,452 121

1973 20 1,536 128

1974 28 1,416 118

1975 20 1,284 107

1976 8 1,224 102

1977 16 1,176 98

1978 7 1,056 88

1979 6 1,044 87

1980 7 1,092 91

1981 8 1,128 94

1982 14 1,056 88

1983 5 1,020 85

1984 27 972 81

1985 5 948 79

1986 2 948 79

1987 19 948 79

8. The empirical 95th percentile of the annual beta/gamma MPM for all locations for 1962

was determined.

January 1963 Through August 1963 

For January 1963 through August 1963, the following was done: 

1. Only the room air samples were selected for assessment.

2. Blank alpha and beta/gamma monthly average air concentrations were assigned average

alpha and average beta/gamma air concentration values of 0.001 pCi/m3

 and 0.01 pCi/m3,

respectively. This corresponded to the lowest alpha and beta/gamma monthly average air

concentrations reported for any sample location in the data set.

3. All unreported air concentrations (i.e., a given month/location combination was not

reported) were assigned an average alpha and average beta/gamma air concentration

values of 0.001 pCi/m3and 0.01 pCi/m3, respectively.
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

 September 18,2017

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4. Any location that was reported at least once in January 1963 through August 1963 was

assumed to have eight monthly means for the alpha air concentration and eight monthly

means for the beta/gamma air concentration.

5. The data for January 1963 through August 1963 was merged with the September 1963

through December 1963 data discussed in the section below.

September 1963 Through 1987 

The reported September 1963 through 1987 BZ locations that were greater than or equal to 1% 

of the reference MPC were converted back to a monthly average air concentration. This includes 

any site specific adjustment factors to the MPC or DCG identified in (LBNL 1963). These are 

provided in items 2 and 3 below. 

1. For each location, year, and month in the main dataset that were referenced to a specific

radionuclide percent MPC, the MPC's are changed to the corresponding MPC, as shown

in the table below. This was necessary to back calculate to air concentrations for these

specific locations.

Table B-3. Filter Queen BZ Locations Referenced to a Radionuclide-Specific 

Percent MPC.

Year Month

MPC 

(pCi/m3) Radionuclide IDa

1981 6 70

Natural 

Uranium 1981-6-18-310

1979 3 300 I-125 1979-3-74-363-R

1979 4 6 Am-241 1979-4-50-307W

1980 5 6 Cm-243 1980-5-70A-129-3

1980 5 6 Cm-243 1980-5-70A-129-1

1980 5 6 Cm-243 1980-5-70A-145-2

1980 5 6 Cm-243 1980-5-70A-129-2

1980 5 6 Cm-243 1980-5-70A-129-4

1980 5 6 Cm-243 1980-5-70A-145-1

a. Identifier consisting of year and month, and building, room, and location.

2. Alpha percent MPC/DCG conversion to average monthly air concentrations in pCi/m3:

a. September 1963 through December 1970:

Alpha average monthly air concentration = Alpha % MPC × 0.4 pCi/m3

/100

Where:

0.4 pCi/m3 = Unknown alpha MPC (LBNL 1963). 
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Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

 September 18,2017

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information that is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.

b. January 1971 through February 1979:

Alpha average monthly air concentration = Alpha % MPC × (0.4 pCi/m3/2)/100 

Where:

0.4 pCi/m3 = unknown alpha MPC (LBNL 1963) 

2 = Unknown alpha MPC adjustment factor (LBNL 1963). 

c. March 1979 through December 1987:

Alpha average monthly air concentration = Alpha % MPC × (0.6 pCi/m3/3)/100 

Where:

0.6 pCi/m3 = Unknown alpha MPC (ERDA 1975). 

3 = Unknown alpha MPC adjustment factor (LBNL 1963). 

3. Beta/gamma percent MPC/DCG conversion to average monthly air concentrations in

pCi/m3

:

a. September 1963 through February 1979:

Beta/gamma average monthly air concentration = Beta/Gamma % MPC 

× 100 pCi/m3/100 

Where:

100 pCi/m3 = Unknown beta/gamma MPC (LBNL 1963). 

b. March 1979 through December 1987:

Beta/gamma average monthly air concentration = Beta/Gamma % MPC 

× (300 pCi/m3

/3)/100 

Where:

300 pCi/m3 = Unknown beta/gamma MPC (ERDA 1975). 

3 = Unknown beta/gamma MPC adjustment factor (LBNL 1963). 

Those BZ locations that were not reported were assumed to have a censored air concentration 

limit equal to 1% of the reference MPC/DCG including site-specific adjustment factors in items 

1 and 2 above. This corresponds to an average alpha air concentration value of 0.004 pCi/m3 for 

September 1963 to 1970 and 0.002 pCi/m3 for 1971 to 1987. This corresponds to an average 

beta/gamma air concentration value of 1 pCi/m3

 for September 1963 to 1987.
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Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

 September 18,2017

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The number of Filter Queen locations sampled per year are listed in Table B-4 below. Before

1971, the number of locations sampled were obtained from the annual summary reports that 

existed for those years. For 1971 and later, the number of locations sampled per year was based 

on counting the number of Filter Queen locations excluding any hood and exhaust Filter Queen

locations in the monthly air sample computer printouts. 

Table B-4. Filter Queen BZ Locations Sampled. 

Year

Number of

Locations Reference

1964 135 LBNL 1963

1965 134 LBNL 1963

1966 145 LBNL 1963

1967 164 LBNL 1963

1968 169 LBNL 1963

1969 159 LBNL 1963

1970 146 LBNL 1963

1971 130 LRL-B 1971

1972 121 LRL-B 1973a

1973 128 LRL-B 1973b

1974 118 LRL-B 1974

1975 107 LRL-B 1975

1976 102 LRL-B 1976

1977 98 LRL-B 1977

1978 88 LRL-B 1978

1979 87 LRL-B 1979

1980 91 LRL-B 1980

1981 94 LRL-B 1981

1982 88 LRL-B 1982

1983 85 LRL-B 1983

1984 81 LRL-B 1984

1985 79 LRL-B 1985

1986 79a Not applicable

1987 79a Not applicable

1993 78 LBNL 1993

a. No data available for this year. 1985 number of air sampling 

locations assumed.

For each year the annual average air concentration was determined by the following:

1. A matrix of the number of sampling locations times 12 months was created. For 

example, in 1970 there were 146 sampling locations. The matrix would consist of 

146 × 12 = 1752 elements. 

2. Each annual matrix was filled in with reported air concentration results that were 1% or 

greater of the reference MPC/DCG. When no alpha result is reported for a given month, 
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Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

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an average alpha air concentration value of 0.004 pCi/m3 for September 1963 to 1970 and 

0.002 pCi/m3 for 1971 to 1987 were substituted. When no beta result is reported for a 

given month, an average beta air concentration value of 1 pCi/m3 for September 1963 to 

1987 was substituted. 

3. The alpha annual average air concentration for each BZ location was determined by

averaging the alpha air concentrations for the year. This is the MPM for each location.

4. The beta/gamma annual average air concentration for each BZ location was determined

by averaging the beta/gamma air concentrations for the year. This is the MPM for each

location.

5. The empirical 95th percentile of the annual alpha MPM for all locations for all years was

determined.

6. The empirical 95th percentile of the annual beta MPM for all locations for all years was

determined.

December 1984

The December 1984 monthly gap data was determined by the following method and was merged 

with the above data: 

1. Only the room Filter Queen, and charcoal samples for gaseous activity were selected.

2. Results where either the alpha result is ≥0.002 pCi/m3 or the beta result is ≥1 pCi/m3 were

selected. These values corresponded to 1% or greater of the reference MPCs used for the

data above.

3. Alpha results that were not reported for charcoal filter results that only measure

beta/gamma activity from gaseous samples were assigned a value of 0.002 pCi/m3

.

4. This data for the December 1984 monthly gap was merged with the data for September

1963 to 1987 discussed in the previous section.

January 1993 Through June 1993 

The January 1993 to June 1993 air concentration data listed six months of data for each Filter 

Queen sampling location. The 1993 annual average air concentration was determined by the 

following method: 

1. Only the room Filter Queen locations were selected.
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Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

 September 18,2017

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2. Alpha and beta/gamma results that were less than or equal to zero were assumed to be 

equal to the minimum non-zero results for the alpha and beta/gamma results reported in 

the data set, respectively. 

3. The alpha annual average air concentration (the MPM) for each BZ location was 

determined by averaging the alpha air concentrations for the year.

4. The beta/gamma annual average air concentration (the MPM) for each BZ location was 

determined by averaging the beta/gamma air concentrations for the year. 

5. The empirical 95th percentile of the annual alpha MPM for all locations was determined. 

6. The empirical 95th percentile of the annual beta/gamma MPM for all locations was 

determined.
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and Air Sampling at the Lawrence Berkeley National Laboratory (Rev. 00)

September 18, 2017

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This document represents preliminary positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any information that 

is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.

Table B-5. Alpha BZ Data Details. 

Year

Uncensored

Positive

Resultsa

Uncensored 

Zero

Results

Censored 

Negative 

Results

Censored 

Null

Resultsb

Censored 

Unreported

Resultsc

Censored 

Unavailable 

Resultsd

Total 

Months

Number of 

Air 

Sampling

Locations Units

1962 1066 0 0 711 1463 0 3240 270 pCi/m3

1963 858 0 0 330 1020 0 2208 184 Percent MPC/

pCi/m3

1964 17 0 0 8 1595 0 1620 135 Percent MPC

1965 18 0 0 6 1584 0 1608 134 Percent MPC

1966 9 0 0 8 1723 0 1740 145 Percent MPC

1967 11 0 0 11 1946 0 1968 164 Percent MPC

1968 17 1 0 4 2006 0 2028 169 Percent MPC

1969 9 2 0 5 1892 0 1908 159 Percent MPC

1970 15 0 0 5 1732 0 1752 146 Percent MPC

1971 20 1 0 3 1536 0 1560 130 Percent MPC

1972 27 8 0 0 1417 0 1452 121 Percent MPC

1973 8 11 0 1 1516 0 1536 128 Percent MPC

1974 16 7 0 5 1388 0 1416 118 Percent MPC

1975 8 12 0 0 1264 0 1284 107 Percent MPC

1976 5 3 0 0 1216 0 1224 102 Percent MPC

1977 7 9 0 0 1160 0 1176 98 Percent MPC

1978 5 1 0 1 1049 0 1056 88 Percent MPC

1979 4 2 0 0 1038 0 1044 87 Percent MPC

1980 7 0 0 0 1085 0 1092 91 Percent MPC

1981 6 2 0 0 1120 0 1128 94 Percent MPC

1982 11 2 0 1 1042 0 1056 88 Percent MPC

1983 4 1 0 0 1015 0 1020 85 Percent MPC

1984 13 14 0 5 940 0 972 81 Percent MPC/

pCi/m3

1985 2 1 0 2 390 553 948 79 pCi/m3

1986 1 1 0 0 77 869 948 79 Percent MPC
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is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.

Year

Uncensored

Positive

Resultsa

Uncensored 

Zero

Results

Censored 

Negative 

Results

Censored 

Null

Resultsb

Censored 

Unreported

Resultsc

Censored 

Unavailable 

Resultsd

Total 

Months

Number of 

Air 

Sampling

Locations Units

1987 11 8 0 0 376 553 948 79 Percent MPC

1993e 581 579 193 Not 

applicable

Not 

applicable

Not 

applicable

Not 

applicable 78 pCi/m3

a. Uncensored results were reported positive results for any year or reported zero results in the monthly summary report data for 1963 through 1987, and the 

1993 individual air sample data. 

b. Null results were blank entries in the reported data for the sampling location. 

c. Unreported results were locations that were not sampled every month in the 1962 through August 1963 computer printout data. Unreported results were 

locations that were not reported in the monthly summary report data for September 1963 through 1987, because they were below the percent MPC reporting 

limit.

d. Unavailable results were monthly summary report air sample information that were not available for 1985 through 1987.

e. 1993 was an average of the January to June individual (i.e., daily or weekly) air sample results.
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and Gamma Bioassay 

and Air Sampling at the Lawrence Berkeley National Laboratory (Rev. 00)

September 18, 2017

Page 99 of 103

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Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions unless specifically marked as such. 

This document represents preliminary positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any information that 

is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.

Table B-6. Beta/Gamma BZ Data Details. 

Year

Uncensored

Positive

Resultsa

Uncensored 

Zero

Results

Censored 

Negative 

Results

Censored 

Null

Resultsb

Censored 

Unreported

Resultsc

Censored 

Unavailable 

Resultsd

Total 

Months

Number of 

Air 

Sampling 

Locations Units

1962 1773 0 0 4 1463 0 3240 270 pCi/m3

1963 1183 0 0 5 1020 0 2208 184 Percent MPC/

pCi/m3

1964 7 0 0 18 1595 0 1620 135 Percent MPC

1965 5 0 0 19 1584 0 1608 134 Percent MPC

1966 6 0 0 11 1723 0 1740 145 Percent MPC

1967 10 0 0 12 1946 0 1968 164 Percent MPC

1968 3 12 0 7 2006 0 2028 169 Percent MPC

1969 3 8 0 5 1892 0 1908 159 Percent MPC

1970 2 13 0 5 1732 0 1752 146 Percent MPC

1971 16 6 0 2 1536 0 1560 130 Percent MPC

1972 32 3 0 0 1417 0 1452 121 Percent MPC

1973 16 4 0 0 1516 0 1536 128 Percent MPC

1974 24 4 0 0 1388 0 1416 118 Percent MPC

1975 15 4 0 1 1264 0 1284 107 Percent MPC

1976 7 1 0 0 1216 0 1224 102 Percent MPC

1977 14 2 0 0 1160 0 1176 98 Percent MPC

1978 5 2 0 0 1049 0 1056 88 Percent MPC

1979 4 2 0 0 1038 0 1044 87 Percent MPC

1980 7 0 0 0 1085 0 1092 91 Percent MPC

1981 6 2 0 0 1120 0 1128 94 Percent MPC

1982 7 7 0 0 1042 0 1056 88 Percent MPC

1983 2 3 0 0 1015 0 1020 85 Percent MPC

1984 24 5 3 0 940 0 972 81 Percent MPC/

pCi/m3

1985 4 1 0 0 390 553 948 79 pCi/m3

1986 1 1 0 0 77 869 948 79 Percent MPC
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and Gamma Bioassay 

and Air Sampling at the Lawrence Berkeley National Laboratory (Rev. 00)

September 18, 2017

Page 100 of 103

This is a working document prepared by NIOSH’s Division of Compensation Analysis and Support (DCAS) or its contractor for use in discussions with the ABRWH or its Working Groups or 

Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or ABRWH (or their technical support and review contractors) positions unless specifically marked as such. 

This document represents preliminary positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any information that 

is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.

Year

Uncensored

Positive

Resultsa

Uncensored 

Zero

Results

Censored 

Negative 

Results

Censored 

Null

Resultsb

Censored 

Unreported

Resultsc

Censored 

Unavailable 

Resultsd

Total 

Months

Number of 

Air 

Sampling 

Locations Units

1987 8 11 0 0 376 553 948 79 Percent MPC

1993e 688 114 548 Not 

applicable

Not 

applicable

Not 

applicable

Not 

applicable 78 pCi/m3

a. Uncensored results were reported positive results for any year or reported zero results in the monthly summary report data for 1963 through 1987, and the 

1993 individual air sample data. 

b. Null results were blank entries in the reported data for the sampling location. 

c. Unreported results were locations that were not sampled every month in the 1962 through August 1963 computer printout data. Unreported results were 

locations that were not reported in the monthly summary report data for September 1963 through 1987, because they were below the percent MPC reporting 

limit.

d. Unavailable results were monthly summary report air sample information that were not available for 1985 through 1987.

e. 1993 was an average of the January to June individual (i.e., daily or weekly) air sample results.
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

 September 18, 2017

Page 101 of 103

This is a working document prepared by NIOSH’s Division of Compensation Analysis and Support (DCAS) or its contractor for use in discussions 

with the ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or 

ABRWH (or their technical support and review contractors) positions unless specifically marked as such. This document represents preliminary 

positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any 

information that is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.

ATTACHMENT C 

Short-Lived Radionuclide Exclusions

LBNL air samples were typically counted 72 hours after removal to allow for decay of the shortlived radon and thoron daughters (Peck 1964). There was no decay correction applied to these 

air samples when the results were reported. 

To determine if short-lived nuclides are plausible when assigning doses based on air samples, the 

BZ air concentrations from the dose reconstruction (DR) methodology were decay-corrected 

back 72 hours to the assumed time of collection stop. Short-lived for this purpose is defined as 

having a half-life less than 20 hours. The radionuclides along with their decay-corrected average 

air concentrations are shown in Table C-1. 

Table C-1. Radionuclides with Half-Lives Less than 20 Hours. 

Radionuclide Half-Life

Decay-Corrected Annual Average Air 

Concentration (pCi/m3)

In-112 14.97 m 6.79E+87

U-239 23.45 m 1.17E+56

Sc-49 57.2 m 2.26E+23

Ga-68 67.71 m 6.69E+19

F-18 109.77 m 2.94E+12

Nd-149 1.728 h 1.46E+13

Ir-195 2.5 h 1.95E+09

Ac-228 6.16 h 1.39E+04

Te-127 9.35 h 8.73E+02

Pb-212 10.64 h 4.57E+02

K-42 12.36 h 2.38E+02

Cu-64 12.701 h 5.47E+02

Nb-90 14.6 h 1.28E+02

Na-24 15 h 1.17E+02

Zr-97 16.9 h 8.04E+01

Pt-197 18.3 h 6.42E+01

C-11 20.39 m 1.01E+70

Cu-60 23.7 m 1.52E+55

Zn-63 38.47 m 1.52E+35

Ag-104 69.2 m 8.44E+18

Ac-224 2.78 h 3.90E+08

Tc-99m 6.015 h 3.29E+05

Cs-127 6.25 h 1.34E+04

Zn-62 9.186 h 1.07E+03

Ta-175 10.5 h 3.81E+02

Y-86 14.74 h 3.88E+01

Br-76 16.2 h 5.29E+01

Zr-86 16.5 h 7.17E+01

Co-55 17.54 h 5.50E+01
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

 September 18, 2017

Page 102 of 103

This is a working document prepared by NIOSH’s Division of Compensation Analysis and Support (DCAS) or its contractor for use in discussions 

with the ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or 

ABRWH (or their technical support and review contractors) positions unless specifically marked as such. This document represents preliminary 

positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any 

information that is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.

The external doses based on air submersion assessment indicates radionuclides with half-lives up 

to around six hours yield unrealistically high doses and would likely exceed the monthly 

administrative external dose limits for a worker. This data is presented in Table C-2. 

Table C-2. External Doses Based on Air Submersion. 

Emission 

Type Radionuclide

Annual 

Breathing Zone 

Air 

Concentration 

(pCi/m3)

FGR No. 12a 

Air Submersion 

Dose 

Coefficient (Sv 

per Bq s m-3)

Annual Dose 

Rate (rads/yr)

Monthly Dose 

(rads)

Over 

Monthly 

Dose Limit Half-Life

Branching 

Fraction/ 

Photon Yield

Beta In-112 6.79E+87 2.60E-15 3.43E+83 2.86E+82 Yes 14.97 m 0.44

Beta U-239 1.17E+56 2.17E-15 4.94E+51 4.11E+50 Yes 23.45 m 1

Beta Sc-49 2.26E+23 1.93E-16 8.48E+17 7.06E+16 Yes 57.2 m 1

Beta Ga-68 6.69E+19 4.58E-14 5.96E+16 4.97E+15 Yes 67.71 m 1

Beta F-18 2.94E+12 4.90E-14 2.80E+09 2.33E+08 Yes 109.77 m 1

Beta Nd-149 1.46E+13 1.81E-14 5.13E+09 4.28E+08 Yes 1.728 h 1

Beta Ir-195 1.95E+09 2.32E-15 8.82E+04 7.35E+03 Yes 2.5 h 1

Beta Ac-228 1.39E+04 4.78E-14 1.29E+01 1.08E+00 Yes 6.16 h 0.997

Beta Te-127 8.73E+02 2.42E-16 4.11E-03 3.42E-04 No 9.35 h 1

Beta Pb-212 4.57E+02 6.87E-15 6.11E-02 5.09E-03 No 10.64 h 1

Beta K-42 2.38E+02 1.46E-14 6.76E-02 5.63E-03 No 12.36 h 1

Beta Cu-64 5.47E+02 9.10E-15 9.69E-02 8.08E-03 No 12.701 h 0.39

Beta Nb-90 1.28E+02 2.17E-13 5.41E-01 4.51E-02 No 14.6 h 1

Beta Na-24 1.17E+02 2.13E-13 4.85E-01 4.04E-02 No 15 h 1

Beta Zr-97 8.04E+01 9.02E-15 1.41E-02 1.18E-03 No 16.9 h 1

Beta Pt-197 6.42E+01 1.01E-15 1.26E-03 1.05E-04 No 18.3 h 0.44

Gamma C-11 1.01E+70 4.89E-14 9.58E+66 7.99E+65 Yes 20.39 m 2.43E-06

Gamma Cu-60 1.52E+55 1.98E-13 5.87E+52 4.90E+51 Yes 23.7 m 1.99E+00

Gamma Zn-63 1.52E+35 5.32E-14 1.57E+32 1.31E+31 Yes 38.47 m 1.73E-01

Gamma Ag-104 8.44E+18 1.32E-13 2.17E+16 1.81E+15 Yes 69.2 m 3.06E+00

Gamma Ac-224 3.90E+08 9.00E-15 6.82E+04 5.69E+03 Yes 2.78 h 6.72E-01

Gamma Tc-99m 3.29E+05 5.89E-15 3.77E+01 3.14E+00 Yes 6.015 h 5.12E-02

Gamma Cs-127 1.34E+04 1.93E-14 5.04E+00 4.20E-01 Yes 6.25 h 9.17E-01

Gamma Zn-62 1.07E+03 2.07E-14 4.31E-01 3.59E-02 No 9.186 h 8.98E-01

Gamma Ta-175 3.81E+02 4.55E-14 3.37E-01 2.81E-02 No 10.5 h 1.28E+00

Gamma Y-86 3.88E+01 1.79E-13 1.35E-01 1.13E-02 No 14.74 h 3.20E+00

Gamma Br-76 5.29E+01 1.34E-13 1.38E-01 1.15E-02 No 16.2 h 1.73E+00

Gamma Zr-86 7.17E+01 1.28E-14 1.79E-02 1.49E-03 No 16.5 h 1.21E+00

Gamma Co-55 5.50E+01 9.78E-14 1.05E-01 8.73E-03 No 17.54 h 1.31E+00

a. EPA (1993). 

A 1953 memorandum about “Sampling Methods and Requirements for Estimating Airborne 

Radioparticulate Hazards” (Thaxter 1953) indicated that because LBNL was a research facility, 

technical contamination was not tolerated as it could invalidate weeks of research. LBNL 

vigorously sought no airborne contamination. They used high-efficiency exhaust air cleaning in 

their enclosures. Nuisance contamination levels were lower by several orders of magnitude than 

permissible levels on the health basis. 

Air samples were changed weekly in locations of moderate experimental activity and daily in 

locations of intense experimental activity at LBNL. Glovebox manifolds and rooms that 

contained gloveboxes were air sampled. Air samples were surveyed daily to check for hot

samples. 
White Paper Method to Assess Internal Dose Using Gross Alpha, Beta, and 

Gamma Bioassay and Air Sampling at the Lawrence Berkeley 

National Laboratory (Rev. 00)

 September 18, 2017

Page 103 of 103

This is a working document prepared by NIOSH’s Division of Compensation Analysis and Support (DCAS) or its contractor for use in discussions 

with the ABRWH or its Working Groups or Subcommittees. Draft, preliminary, interim, and White Paper documents are not final NIOSH or 

ABRWH (or their technical support and review contractors) positions unless specifically marked as such. This document represents preliminary 

positions taken on technical issues prepared by NIOSH or its contractor. NOTICE: This report has been reviewed to identify and redact any 

information that is protected by the Privacy Act 5 USC §552a and has been cleared for distribution.

High count rate reading air samples were investigated. These investigation air samples are found 

in various special or investigation air sample reports (LBL 1965, 1967, 1975, 1988, 1995). A 

limited review of these various special air sample reports indicates that the lowest measured 

alpha and beta/gamma activities were a small fraction (less than 1%) of the unknown MPC or 

derived air concentration (DAC). The unknown MPC or DAC was typically used to determine 

the percent of the MPC or DAC in these investigation air sample reports. Starting in 1971, 

LBNL used an alpha MPC of 0.2 pCi/m3 (LBNL 1988) to compare most air concentrations in 

these special investigations air sample reports. This was a factor of 2 lower than the National 

Bureau of Standards Handbook 69 (NBS 1959, revised 1963) value of 0.4 pCi/m3 and a factor of 

three lower than the ERDA 0524 (ERDA 1975) and DOE 5480 (DOE 1981) values of 0.6 

pCi/m3

. LBNL used a beta/gamma MPC of 100 pCi/m3 throughout. This was a factor of three 

lower than the ERDAM 0524 and DOE 5480 values of 300 pCi/m3. 

The special investigation air sample data indicates that air samples less than 1% of the MPC or 

DAC were investigated. The short-lived radionuclides in Table 1 are beta/gamma emitters. One 

percent of the MPC or DAC results in a beta/gamma air sample investigation limit of 1 pCi/m3. 

One reference provides alpha and beta/gamma air sample counting results immediately and after 

a 48-hour decay period after removal (Patterson 1957). The data indicates that the radon and 

thoron daughters contribute to an initial count rate approximately 30 to 60 times higher for alpha 

air samples counted immediately after sample removal. The radon and thoron daughters 

contribute to an initial count rate approximately three times higher for the beta/gamma air 

samples counted immediately after sample removal. Accounting for radon/thoron daughter 

decay, these beta/gamma air samples would read around three pCi/m3 immediately after removal. 

The half-life cutoff in the LBNL DR Methodology was around 12 hours. This still included 

decay-corrected beta emitters on the order of 100 pCi/m3

. This also included decay-corrected 

gamma emitters on the order of 10 pCi/m3. 

The above indicates that short-lived radionuclide activities decay-corrected back 72 hours, such 

as those in Table 1, cannot be produced at levels to maintain the continuous exposures without 

resulting in significant field contamination in the work areas. It is also evident, based on the 

LBNL air sampling program, that these shorter-lived radionuclides in Table 1 would have been 

detected and investigated well before reaching these decay-corrected air concentrations levels. 

Based on the above, short-lived radionuclides with half-lives less than 12.7 hours were excluded 

from the potential unmonitored radionuclides. 

The short-lived radionuclides excluded were:

1. Gamma emitters: 

Carbon-11, 60Cu, 63Zn, 104Ag, 224Ac, 99mTc, 127Cs, 62Zn, 175Ta.

2. Beta emitters:

Indium-112, 239U, 49Sc, 68Ga, 18F, 149Nd, 195Ir, 228Ac, 127Te, 212Pb, 42K.